Download - AL.NIKOLOV, D.POPOV NPP KOZLODUY
1BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISA2006 FISA2006 - LONG-TERM - LONG-TERM RESEARCH AND RESEARCH AND TRAINING FOR SUSTAINABLE DEVELOPMENT TRAINING FOR SUSTAINABLE DEVELOPMENT
IN THE NUCLEAR FIELD IN THE NUCLEAR FIELD FOUNDED BY THE FOUNDED BY THE EUROPEAN COMMISSIONEUROPEAN COMMISSION
ALNIKOLOV DPOPOV ALNIKOLOV DPOPOV
NPP KOZLODUYNPP KOZLODUY
2BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
ACKNOWLEDGEMENTS
Thanks tobull AssProf DrScEngIv Ivanov from Technical University of Sofia
- to have assured our attendance to FISArsquo06
bull Prof Aragones UPM Spain G LoumlwenhielmSKI Sweden T Shulenberg FZKGermany profB Bazargan-Sabet INPL-Ecole des Mines de Nancy France J-P Massoud EDF France D Warin CEA France J-Y Blanc CEA France M McDermott NNC Ltd GB W Raskob FZKGermany J-C Micaelli IRSN France JTuunanen TVO Finland
- to have sent personally their presentations in FISArsquo06
bull Mrs M Antoine secretary in Unit J4 DG RTD
- to have sent web links to FP-6
3BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 13-16 March Luxembourg
FISA=FIssion SAfety The FISA covers the entire spectrum of reactor safety research and trainingeducation in new nuclear fields that was included in last EURATOMrsquo Framework Program FP-6
Up to 350 participants of old and new EU countries and EU candidates but also from USA Switzerland Russia Ukraine Korea Japan Turkey and others not to mention international organisations such as IAEAOECDNEA
4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 what expectations from
EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip
hellipand also to examine the future nuclear alternatives
5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Energy needs of EU Community
EU25 Growth of import dependency
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo
FISArsquo06)
6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTS
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
KEEPING THE NUCLEAR OPTION OPEN NEED FOR DRASTIC DECREASE OF THE
CARBON INTENSITY IN THE ECONOMY ADDRESSING THE CHALLENGES OF
GLOBAL WARMING EMPHASIS ON THE SAFETY OF
INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY
EC Green Paper 8 March 2006
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
2BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
ACKNOWLEDGEMENTS
Thanks tobull AssProf DrScEngIv Ivanov from Technical University of Sofia
- to have assured our attendance to FISArsquo06
bull Prof Aragones UPM Spain G LoumlwenhielmSKI Sweden T Shulenberg FZKGermany profB Bazargan-Sabet INPL-Ecole des Mines de Nancy France J-P Massoud EDF France D Warin CEA France J-Y Blanc CEA France M McDermott NNC Ltd GB W Raskob FZKGermany J-C Micaelli IRSN France JTuunanen TVO Finland
- to have sent personally their presentations in FISArsquo06
bull Mrs M Antoine secretary in Unit J4 DG RTD
- to have sent web links to FP-6
3BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 13-16 March Luxembourg
FISA=FIssion SAfety The FISA covers the entire spectrum of reactor safety research and trainingeducation in new nuclear fields that was included in last EURATOMrsquo Framework Program FP-6
Up to 350 participants of old and new EU countries and EU candidates but also from USA Switzerland Russia Ukraine Korea Japan Turkey and others not to mention international organisations such as IAEAOECDNEA
4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 what expectations from
EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip
hellipand also to examine the future nuclear alternatives
5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Energy needs of EU Community
EU25 Growth of import dependency
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo
FISArsquo06)
6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTS
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
KEEPING THE NUCLEAR OPTION OPEN NEED FOR DRASTIC DECREASE OF THE
CARBON INTENSITY IN THE ECONOMY ADDRESSING THE CHALLENGES OF
GLOBAL WARMING EMPHASIS ON THE SAFETY OF
INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY
EC Green Paper 8 March 2006
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
3BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 13-16 March Luxembourg
FISA=FIssion SAfety The FISA covers the entire spectrum of reactor safety research and trainingeducation in new nuclear fields that was included in last EURATOMrsquo Framework Program FP-6
Up to 350 participants of old and new EU countries and EU candidates but also from USA Switzerland Russia Ukraine Korea Japan Turkey and others not to mention international organisations such as IAEAOECDNEA
4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 what expectations from
EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip
hellipand also to examine the future nuclear alternatives
5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Energy needs of EU Community
EU25 Growth of import dependency
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo
FISArsquo06)
6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTS
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
KEEPING THE NUCLEAR OPTION OPEN NEED FOR DRASTIC DECREASE OF THE
CARBON INTENSITY IN THE ECONOMY ADDRESSING THE CHALLENGES OF
GLOBAL WARMING EMPHASIS ON THE SAFETY OF
INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY
EC Green Paper 8 March 2006
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
FISArsquo06 what expectations from
EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip
hellipand also to examine the future nuclear alternatives
5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Energy needs of EU Community
EU25 Growth of import dependency
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo
FISArsquo06)
6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTS
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
KEEPING THE NUCLEAR OPTION OPEN NEED FOR DRASTIC DECREASE OF THE
CARBON INTENSITY IN THE ECONOMY ADDRESSING THE CHALLENGES OF
GLOBAL WARMING EMPHASIS ON THE SAFETY OF
INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY
EC Green Paper 8 March 2006
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Energy needs of EU Community
EU25 Growth of import dependency
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo
FISArsquo06)
6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTS
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
KEEPING THE NUCLEAR OPTION OPEN NEED FOR DRASTIC DECREASE OF THE
CARBON INTENSITY IN THE ECONOMY ADDRESSING THE CHALLENGES OF
GLOBAL WARMING EMPHASIS ON THE SAFETY OF
INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY
EC Green Paper 8 March 2006
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTS
Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06
KEEPING THE NUCLEAR OPTION OPEN NEED FOR DRASTIC DECREASE OF THE
CARBON INTENSITY IN THE ECONOMY ADDRESSING THE CHALLENGES OF
GLOBAL WARMING EMPHASIS ON THE SAFETY OF
INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY
EC Green Paper 8 March 2006
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Features of Gen IV
1 High Safety Level
2 Good Economy
21 High efficiency (η~ up to 50)
22Possibility to develop H2 industry
3 Proliferation resistance (Minor Actinides)
EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts
Water-Cooled 1 Super-Critical Water Reactor (SCWR)Gas-cooled 2Very-High Temperature Reactor (VHTR) 3Gas-cooled Fast Reactor (GCFR)Liquid Metal-Cooled 4 Sodium cooled Fast Reactor (SFR) 5 Lead Fast Reactor (LFR) Pb-Bi cooledNon-Classical 6 Molten Salt cooled Reactor (MSR)
6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT
(~2030)
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor
FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to
bull deliver Electricitybull deliver Hydrogen
From breeder to burner and recycling minor actinides
closed fuel cycle for efficient conversion of fertile uranium and management of actinides
Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant
Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod
Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products
bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds
Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)
PARTICIPANTS
National Nuclear Corporation Ltd NNC
Nexia Solutions NEXIA
Commissariat agrave lrsquoEnergie Atomique CEA
Empresarios Agrupados Internacional SA EA
Framatome ANP SAS FANP SAS
Joint Research Centre ndash ITU and IE JRC
Nuclear Research and Consultancy Group NRG
Paul Scherrer Institut PSI
Delft University of Technology TUD
InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa
CIRTEN-UNIPI
The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent
performance in actinide management It is rated good in
safety economics and in proliferation resistance and
physical protectionCERCER plate fuel High power density ~ 100 MWm^3
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod
Development Strategy
Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030
ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to
prototypedemo)Synergies with HTR
bull Helium-gas cooledbull High temperature materials and components
ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR
750
00
1950
00
120
0
689
14 436
656
25
990
00
120
000
2650
4700
15 500
68 9
2500
00
7000
640
00
673827
908
000
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System
FEATURES Lead-cooled by natural convection fast-
neutron spectrum Fuel = MOX Outlet temperature of the helium 550 C up
to 850 C depending on the advanced materials to be used
Possible tobull deliver Electricitybull deliver Hydrogenbull deliver potable Water
Full actinide recycle fuel cycle with central or regional fuel cycle facilities
Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod
Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SFR ndash Sodium-Cooled Fast Reactor System
The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System
The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent
potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is
primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management
system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System
The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor
In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor
The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System
The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency
The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings
The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem
The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping
The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research
Information Database and Knowledge Management Links 25 PARTICIPANTS
HU AEKI VEIKI
CZ NRI CTU NSTC
SK VUJE STU CENS
FI FORTUM VTT LUT
EU JRC IE
DE GRS FZR
NL NRG
BG INRNE TUS ENIN REL
RU RRCKI OKBGP EREC
UA NPPOSI SSTCNRS ISTC
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental
bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed
Project Objectives
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP3 Operational SafetyFive task groups Group A Basic VVER safety items
Task Discussion identification and recommendations of the safety research needs
Group B Experimental facilities and code validationTask Information exchange in computer code validation
Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER
Group D Safety of refuelling pools Task Collection of activities in the field of spent fuel storage pool safety Group E Steering activities in operational safety In task group B a draft report was prepared Identification of the VVER experimental facilities and
description of the available and missing experimental capabilities
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary
components Fatigue DosimetryUpgrading and extending the VERLIFE code (PTS P-T diagram surveillance Master
Curve etc) and discussion of VERLIFE experience and upgradeCollecting and exchanging new information on VVER Life Management practices
(national solutions and practices)Collecting new information on VVER material ageing and life performance (eg Irradiation
effect on cladding application of Master Curve annealing steam generator corrosion etc)
Determining fields where new common research is requiredDefine further necessary (common) RampD and prepare common proposals
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young
specialists in nuclear) for all WPs
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod
WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM SCOPE AND OBJECTIVESFeb 2005 ndash Jan 2008
18 Organizations13 Countries
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
NURESIM PLATFORM
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks
SP1 CORE PHYSICS WP11 Advanced Monte Carlo Methods
bullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH) WP12 Advanced Deterministic Diffusion and Transport Methods
bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)
WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)
WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux
SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHFbull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface
bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer
bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquod
SP3 MULTIPHYSICSReview and specification within the NURESIM
platform of coupling schemes for core analysis based on existing CP and TH core codes
bullAt the nodal level (fuel assembly)bullAt the sub-node level (pin)
Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer
Application to PWR (MSLB) and BWR
A multi-scale analysis of accidental transients with 3D simulation
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules
- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses
Implementation within the NURESIM platform of procedures for propagation of uncertainties
SP5 INTEGRATIONbull Specific training courses on
the SALOME platformbull Assistance in integrating
codesbull Adaptation of the SALOME
platformbull Ensuring consistency and
non-regression
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod
bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY
bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE
bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW
bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-
30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066
SOME USEFUL WEB LINKS
bullhttp www cordiseuropaeufp6bullhttp wwwnuresimorgbullhttp wwweu-nerisnetbullhttpiriaxpiritudelftnl
bull httpgifinelgov bullhttp wwwgcfrorg
Thank you for your attention
- Slide 1
- ACKNOWLEDGEMENTS
- FISArsquo06 13-16 March Luxembourg
- FISArsquo06 what expectations from
- Energy needs of EU Community
- EURATOM FP-6 PROJECTS
- EURATOM FP-6 PROJECTS Generation-IV Innovative Concepts
- Slide 8
- Slide 9
- Slide 10
- Slide 11
- Slide 12
- Slide 13
- Slide 14
- Slide 15
- Slide 16
- Slide 17
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research
- EURATOM FP-6 PROJECTS SAFETY OF EXISTING INSTALLATIONS COVERS ndash VVER Safety Research - contrsquod
- Slide 20
- Slide 21
- Slide 22
- Slide 23
- Slide 24
- Slide 25
- Slide 26
- Slide 27
- Slide 28
- Slide 29
- SOME USEFUL WEB LINKS
-