. / * • •

Croatian Nuclear Society

EUROPEAN NUCLEAR SOCIETY

in co-operation I sponsoredwith IAEA by ENS

8th International Conference on

NUCLEAR OPTIONIN COUNTRIES WITHSMALL AND MEDIUMELECTRICITY GRIDSMay 16-20, 2010, Dubrovnik, Croatia

Proceedings I Bookand I of Abstracts

Editors

Dubravko Pevec, Damir Subašić and Zdenko Šimić

Edited and printed by

Croatian Nuclear Society

Unska 3,10000 Zagreb, Croatiatel: +385 1 6129627, fax: +385 1 6129605e-mail: hnd@nuclear-option.orgweb: nuclear-option.org, nuklearno-drustvo.hr

Editorial note

The views expressed in the papers, the statements made andthe general style adopted are the responsibility of the named authors.Authors are themselves responsible for obtaining the necessarypermission to reproduce copyright material from other sources.

ISBN 978-953-55224-3-0

CIP zapis dostupan u računalnom kataloguNacionalne i sveučilišne knjižnice u Zagrebupod brojem 737765

8th International Conference

NUCLEAR OPTIONIN COUNTRIES WITHSMALL AND MEDIUMELECTRICITY GRIDSMay 16-20, 2010, Dubrovnik, Croatia

Proceedings and Book of Abstracts

Conference Organized byCroatian Nuclear Societyin co-operation with IAEA

Under the Auspices of

EUROPEAN NUCLEAR SOCIETYIAEA

International Atomic Energy Agency

HHEPdd

Ministry of Science,Education and Sports

IRB

Ministry of Economy, Labourand Entrepreneurshup

M Q K1 8 3 2

Croatian Chamber ofEconomy

Fond za fina-nciranje raz-gradnje NEK

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D. PEVEC, Chairman, Croatia

M. Bace, CroatiaH. Boeck, Austria

G. Cognet, FranceM. Čerškov-Klika, CroatiaD. Čorak, CroatiaF. D'Auria, ItalyV. Dimitrijević, USAD. Dodig, CroatiaY. Dragunov, RussiaD. Feretić, CroatiaP. Gaio, USAD. Grgić, CroatiaH. Glaeser, GermanyZ. Heruc, SloveniaT. Hirose, JapanK. Ilieva, BulgariaD. Kavšek, Slovenia

A. Kereszturi, HungaryV. Knapp, Croatia

V. Krošelj, SloveniaV. Kuznetsov, IAEAR. Kyrki-Rajamaki, FinlandS. Lulić, CroatiaN. Malbaša, CroatiaB. Manchev, BulgariaG. Marović, CroatiaB. Mavko, SloveniaV. Mikuličić, CroatiaJ. Mišak, Czech RepublicS. Monti, Italy

N. Novosel, CroatiaH. Perharić, SloveniaB. Petrović, USAI. Plećaš, Serbia

M. Prah, CroatiaS.M.S. Reitsma, SwitzerlandM. Ricotti, ItalyS. Rožman, SloveniaB. Sladonja, CroatiaV. Slugen, SlovakiaA. Stritar, SloveniaZ. V. Stošić, GermanyD. Subašić, Croatia

P. Škola, SloveniaD. Škanata, CroatiaB. M. Tyobeka, IAEAŽ. Tomšić, CroatiaA. Tropp, EstoniaN.B. Trunov, RussiaK. Vrankić, CroatiaM. Zeljko, Croatia

Organising CommitteeZ. ŠIMIĆ, Chairman, Croatia

K. BojićI. IvekovićI. JakićD. Konjarek

K. NodiloD. PehardaD. RašetaM. Subašić

S. ŠadekK. TrontlI. Vuković

8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

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The International Conference "Nuclear Option in Countries with Small and Medium Electricity F"Grids" is the eighth in a series of meetings on the same topics organized biennially by the Croa- 3tian Nuclear Society. This topical conference was initiated in 1996 and the first conference took splace in Opatija, with the following six in Dubrovnik. The conference is organized with intentionto focus on specific aspects of usage of nuclear energy for electricity production in small andmedium countries.

Importance of international cooperation for the assessment of the nuclear option has been rec-ognised by the International Atomic Energy Agency (IAEA). As a result of this recognition, theConference is organized in co-operation with IAEA.

Session topics reflect some current emphasis, such as country energy needs, accommodationon Kyoto restriction on CO2 emission, new reactor technologies, operation and safety of theoperating nuclear power plants. The conference also focuses on the exchange of experience andco-operation in the fields of fuel cycle, radioactive waste management, regulatory practice andliability and insurance for nuclear damage.

Authors' contributions are presented in 6 invited lectures and 66 contributed papers. All thecontributed papers are grouped in 10 sessions:

1. Energy Planning and Nuclear Option (EPNO)

2. Power Reactors and Technologies (PRT)

3. Nuclear Energy and Environment (NEE)

4. Operation and Maintenance Experience (OME)

5. Safety Culture (SC)

6. Nuclear Safety Analyses (NSA)

7. Reactor Physics and Nuclear Fuel Cycle (RPNFC)

8. Radioactive Waste Management and Decommissioning (RWMD)

9. Public Relations (PR)

10. Regulatory Practice and General Papers (RPGP)

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSo

All contributed papers are published. The abstracts are printed in the Book of abstracts, ando Proceedings. It includes also full papers given on the memory stick.

a We would like to express our gratitude to over 170 authors and co-authors that put an extra ef-2 fort into completing their full camera-ready papers. We would also like to thank the sessions'*>. coordinators, reviewers and all those who have helped us in organizing this Conference.

o Acknowledgements are given to the International Atomic Energy Agency and the European Nu-i • clear Society for their support and encouragement.

Also, we are particularly grateful to all the sponsors whose contribution has been essential forthe success of this International Conference. We express our thanks to all those, who throughtheir efforts and participation, have contributed to the Conference success.

Zagreb, May 2010

EDITORS

8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS

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Table of ContentsXI3

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8%• Invited Lectures

IL-01 BlSMARK M . TYOBEKA

Global Status of Nuclear Power 18

IL-02 CHRISTIAN KIRCHSTEIGER

2020/2050 Perspectives for Nuclear Energy in the EU 19IL-03 NATAŠA VUJEC

New Croatian Energy Strategy - Towards sustainable energy 20IL-04 SEBASTIAAN M.S. REITSMA

Nuclear Liability, State of the Art 21

Session 1 Energy Planning and Nuclear Option (EPNO)

Si-12 L. LITVINSKY, O. PURTOV, V. BRONNIKOV, N. VLASENKO, S. SILCHENKO

Concept of State Target Economic Program for Nuclear EnergyDevelopment up to 2020 23

S1-40 N. ČAVLINA, D. RAŠETA, J. LEBEGNER

Comparison of Levelized Costs of New Nuclear, Gas andCoal Power Plants 25

S1-41 J. BAURSKI

Nuclear Co-Generating Plants for Powering and Heating toCleaning the Warsaw's Environment 26

S1-69 Ž. TOMŠIĆ, R. PAŠIČKO

CO2, Coal, and Gas Price Impacts on Nuclear Power PlantCompetitiveness in Croatia 27

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8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS &

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S1-80 V. KNAPP, D. PEVEC, M. MATIJEVIĆ $

On the Potential of Nuclear Fission Energy for Effective Reduction gof Carbon Emission under the Constraint of Uranium Resources -°Use without Spent Fuel Reprocessing 28 g-

3S1-90 I. ANDROČEC, A. ĆURKOVIĆ, T. TARNIK |

Power Generation Strategy Development in Croatia 29 nO

S1-99 I. JAKIĆ, J. LEBEGNER, N. PEROVIĆ IProgramme of Preparatory Activities on Launching First NuclearPower Plant in Croatia 31

Session 2 Power Reactors and Technologies (PRT)

S2-IL-117 Z. V. STOŠIĆ

On the Matter of NPP New Builds 33

S2-IL-23 P.GAIO

Westinghouse AP1000: Leading the Nuclear Renaissance 34S2-11 J. B. MALHERBE, C. E. CLOETE

The South African Pebble Bed Modular Reactor and Its Implicationsfor Residential Power Consumption in Developing Countries 35

S2-39 N. M. S. BERGROTH

Large-Scale Combined Heat and Power (CHP) Generation atLoviisa Nuclear Power Plant Unit 3 36

S2-52 B. PETROVIC, K. BURN, M. CIOTTI, F. FRANCESCHINI, L. CASALINI,M. SAROTTO, M. CARELLI, J. SEJVAR, C. LOMBARDI, JEFF JOHNSON,JORDAN MCKILLOP, D. HARTMANGRUBER

Design Features of the IRIS Reactor to Reduce Collective Doseduring Operation and Maintenance and to Simplify D&D 37

S2-60 Y. N. KUZNETSOV

Nuclear Co-Generation Desalination Complex with VK-300Simplified Boiling Water Reactor 39

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSoU•i Session 3 Nuclear Energy and Environment (NEE)| :Q S3-20 I. PRLIĆ, M. SURIĆ MIHIĆ, G. MAROVIĆ, M. NOVAKOVIĆ, T. MEŠTROVIĆ,2 Z. CEROVACo£. Total Occupational and Possible Public Member Exposure duringj | Characterisation, Conditioning and Securing of Radioactive7 Sealed Sources - A New Dosimetric Concept Using Active^ Electronic Dosimeters 41

S3-22 I. PRLIĆ, G. MAROVIĆ, R. TURK, T. BITUH, M. SURIĆ MIHIĆ, B. SKOKO,T. MEŠTROVIĆ, E. SPITALER, Z. VUČIĆ

TENORM Characterisation, Conditioning and Remediation to beReused in New Products and Associated Possible Public Memberand Occupational Hazard 42

S3-28 I. KODELI, G. GUALDRINI, S. AGOSTEO, D. BROGGIO, L. DE CARLAN,E. GARGIONI, J. M. GOMEZ-ROS, B. GROSSWENDT, C. HUET, R. PRICE,S. ROLLET, B. R. L. SIEBERT, L. STRUELENS, R. TANNER, H. VINCKE,B. WIEGEL, M. ZANKL

Activities of the EUR AD OS Working Group 6 onComputational Dosimetry 43

S3-88 M. MlHALINA, B. GLASER

Determination of Radiological Dilution Factors in the SavaRiver for new Reference Group of Inhabitants DownstreamoftheKrškoNPP 44

Session 4 Operation and Maintenance Experience (OME)

S4-14 P. LOVRENČIČ, D. KAVŠEK

New Fire Protection Inspection Technique 47S4-34 D.CicvARić

Integration of the Ovation Based Distributed Turbine ControlSystem into the Existing Process Information System and FullScope Simulator at NPP Krško 48

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8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

S4-56 P. BUDULAN 2

Successful Operation of the Only CANDU Type Reactor in Europe 49 g

S4-76 M. PAJNIĆ, H. FRANJIĆ, G. SMOLJKIĆ, K. MARKULIN, A. VUČAJNK, F. JARNJAK

Advanced Approach of Reactor Pressure Vessel Head Inspectionand Repair of CRDM J-Weld 50

S4-77 M. PAJNIĆ, A. MATOKOVIĆ, K. MARKULIN, H. FRANJIĆ QAdvanced Approach of Reactor Pressure Vessel In-Service 5Inspection 51

S4-78 M. PAJNIĆ, S. GALOŠIĆ, H. FRANJIĆ, K. MARKULIN

System for Eddy Current Inspection of WER-440/1000 SG's Tubes 52

S4-81 I. KUZLE, D. BOŠNJAK, H. PANDŽIĆ

Auxiliary System Load Schemes in Large Thermal and NuclearPower Plants 53

S4-87 T. BAJS, M. BALIĆ, I. BAŠIĆ, I. VRBANIĆ, B. SEMBER, N. DJETELIĆ

NPP Krško Approach to Pressure Locking and Thermal Binding inMotor Operated Valves 54

S4-89 M. MIHALINA, N. DJETELIĆ

Component Cooling Heat Exchanger Heat Transfer CapabilityOperability Monitoring 55

S4-96 P. SCHIMANN

Requirements and Possibilites for Operational ExperienceFeedback from the Plant's Manufacturer's Point of View 56

S4-98 F. JARNJAK, S. REŠKOVIĆ, E. PICEK

Next Generation of ECT Software for Data Analysisof Steam Generator Tubes 57

S4-102 D. MANDIĆ, M. J. ZILAVY

Turbine Control System Replacement at NPP NEK; SystemSpecifics, Project Experience and Lessons Learned 58

S4-107 M. VAVROUŠ, R. GRACIN

Qualification Practices in Nuclear Industry: Steam GeneratorEddy Current Probe Qualification 60

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eu:* S4-113 M. DUDAŠ2 Automation of Shift Work in Operations 61Q S4-115 Z. BERTALANIĆ, M. PAVLICA, Z. MALJKOVIĆoo High Partial Discharge Levels in Nuclear Power Plantjf Turbo-Generator 62o

Session 5 Safety Culture (SC)

S5-17 A. ČIŽMEK

Nuclear Security and Nuclear Security Culture 64S5-36 R. BIŠĆAN

Supplier Assessment and Auditing Process 65S5-38 B. MANCHEV, B. NENKOVA, E. TOMOV

Quality and Safety Assurance - Priority Task at Nuclear PowerProjects Implementation 66

S5-45 B. BožiN, D. KAVŠEK

Nuclear Oversight Function at Krško NPP 67S5-50 A. ROŽMAN, A. ANDROJNA

The Role of Occupational Health and Safety in Complex OutageServices to NPPs 68

S5-70 A. KUŠAR, D. KAVŠEK

Krško Nuclear Power Plant's Environmental ManagementSystem in Compliance with ISO 14001:2004 69

Session 6 Nuclear Safety Analyses (NSA)

S6-24 T. MAUNA

Sitting Safety Aspects of Second Romanian NPP 72

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8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

S6-29 K. FILIPOV, S. PHILIPOV 2Code Development for Internal Flooding in NPP and Benchmark Analyses 73 8

oS6-37 A. DEL NEVO, M. ADORNI, F. D'AURIA, O. I. MELIKHOV, I. V. ELKIN, "D

V. I. SCHEKOLDIN, M. O. ZAKUTAEV, S. I. ZAITSEV, M. BENČIK |-o

Enlargement of the Assessment Database for Advanced Computer I.Codes in Relation to the VVER Technology: Benchmark on nLB-LOCA Transient in PSB-WER Facility 74 |

S6-48 C. ALLISON, L. SIEFKEN, J. HOHORST, J. BIRCHLEYRecent Improvements in RELAP/SCDAPS1M/MOD3.4 Resultingfrom QUENCH and PARAMETER Bundle Heating and QuenchingExperiments 75

S6-51 S. ŠADEK, D. GRGIĆ, N. DEBRECIN

Corium Behaviour and the Lower Head Thermal Responseafter a Core Meltdown 76

S6-58 I. VRBANIĆ, I. BAŠIĆ, I. VUKOVIĆ

Krško NPP PSA Update with SG BD System Modifications 77S6-59 I. VRBANIĆ, I. BAŠIĆ, A. ANTOLOVIČ

Methodology for Ranking of the NPP Krsko PSR Issues 78S6-63 C. MATTEOLI, G. NACCI, M. CHERUBINI, A. DEL NEVO, F. D'AURIA

Study of CCFL Phenomenon Based on University ofHannover Experiments 79

S6-67 M. CHERUBINI, F. MORETTI, F. DAURIA, S. H. AHN, Y. J. CHO, T. HOEHNE

Independent Assessment of MARS 3D Features: Use ofExperimental Data and CFD Support 80

S6-68 D. GRGIĆ, V. BENČIK, S. ŠADEK, N. ČAVLINA

RELAP5 Modelling of PWR Reactor RTD Bypass 81S6-82 Z. ŠiMić, V. MIKULIČIĆ

On the Screening of Other External Events: Explosions andHazardous Release Evaluation 82

S6-116 D. KONJAREK, T. BAJS, J. VUKOVIĆ

Intermediate Leg SBLOCA - Long Lasting Pressure Transient 83

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.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSa2u:* S6-12O T. BlLIĆ ZABRICc8 Safety Requirements for New Nuclear Facilities 84

oCM

Session 7 Reactor Physics and Nuclear Fuel Cycle (RPNFC)

S7-47 S. MICHALEK, G. FARKAS, J. LIPKA, J. RATAJ, J. HAŠČIK, V. SLUGEN,S. ŠTEVO, A. KOLROS

Determination of Effective Delayed Neutron Fraction forNuclear Reactors 86

S7-53 B. PETROVIC, L. M. HUANG

Minor Actinide Burn in Thermal Spectrum withEnhanced Moderation 88

S7-54 M. KROMAR, B. KURINČIČ

Cycle Power Characteristics of the NPP Krško Fuel 89S7-65 D. PEVEC, K. TRONTL, D. GRGIĆ, R. JEČMENICA, M. MATIJEVIĆ,

T. BELAVIĆ

Upgrade of the FUM ACS 2005 Code Package 90S7-66 J. VuKOvić, D. GRGIĆ, D. KONJAREK

ORIGEN2.1 Cycle Specific Calculation of Krško Nuclear PowerPlant Decay Heat and Core Inventory 91

S7-79 R. JEČMENICA, D. GRGIĆ, D. PEVEC

Prediction Capabilities of Spectral Codes DRAGON,FA2D, and NEWT 92

Session 8 Radioactive Waste Management and Decommissioning (RWMD)

S8-10 I. B. PLEĆAŠ

Mathematical Modelling of Immobilization of Radionuclides 137Csand 60Co in Concrete Matrix 94

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oS8-33 P. ORMAI S

Hungarian Waste Retrieval Program for Enhancing gthe Long-Term Safety of the Near Surface Repository 95 -°

S8-42 A. KNAPP, I. LEVANAT, V. LOKNER I"O

Compensations to Local Communities in the Krško NPP 5.Decommissioning Program 96 n

3S8-43 C. GEAMBASU, A. SORESCU |

EU Support towards Romania to Get Safe Nuclear Waste Management 97S8-55 I. LEVANAT, V. LOKNER, A. RAPIĆ, M. KRALJ, I. MELE, P. STROPNIK,

N. ŽELEZNIK

Revision 2 of the Program of NPP Krško Decommissioningand SF & LILW Disposal 98

Session 9 Public Relations (PR)

S9-16 N. ŽELEZNIK

Mental Models of Radioactivity and Attitudes towardsRadioactive Waste 100

S9-62 I. JENČIČ

Tangible Results of Nuclear Information Centre in Slovenia 101S9-64 K. TRONTL, R. JEČMENICA, D. PEVEC

Public Opinion Survey - Energy - The Present andthe Future - 2009/10 102

Session 10 Regulatory Practice and General Papers (RPGP)

S10-18 N. NOVOSEL, L. ROSANDIC

International Cooperation of the Republic of Croatia in theField of Nuclear Safety 104

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.3 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS

8^ S10-27 Z. BAZSO2 Regulatory Aspect of Periodic Safety Review Performed£ in Nuclear Power Plants in the Slovak Republic 105

S S10-83 S. PLESLIĆ

&- Implementation of Knowledge Management inI R&D Institutions 106

Author Index 107

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8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS

Invited Lectures

Invited Lectures

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IL-01 BlSMARK M. TYOBEKA "n

Global Status of Nuclear Power 18 |E'

IL-02 CHRISTIAN KIRCHSTEIGER2020/2050 Perspectives for Nuclear Energy in the EU 19

IL-03 NATAŠA VUJEC

New Croatian Energy Strategy - Towards sustainable energy 20

IL-04 SEBASTIAAN M.S. REITSMA

Nuclear Liability, State of the Art 21

17

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEhil'M K.'.ili?R.ivV?90.Q2Qs

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| Global Status of Nuclear Power:3 Prospects and Challengesb

3 BlSMARK M. TYOBEKA Global energy requirements and the share of electricity in total energy>•• International Atomic Energy consumption are increasing rapidly, and the contribution of nuclear pow-

Agency, IAEA, Division of er is projected to increase significantly. Out of the 29 countries currentlyNuclear Power using nuclear power for electricity generation, 22 intend to allow newP.O. Box 100 plants to be built, and, of those, the majority are actively supporting theWagramer Strasse 5 increased use of nuclear power, some by providing incentives. Most ofA-1400 Vienna, Austria these countries are expected to build reactors with a generating capacityb.m.tyobeka@iaea.org of o v e r 1000 MW(e). Only three countries continue to have a policy to

phase out the use of nuclear energy in the future by not replacing existingoperating nuclear power plants and with no consideration of the option of new nuclear plants.In addition, a growing number of countries are expressing interest in introducing nuclear power. Of themore than 60 countries that have expressed such an interest in recent years, over 20 are actively consid-ering nuclear power programmes to meet their energy needs and the others have expressed interest inunderstanding the issues associated with the introduction of nuclear power.

The drivers for rising expectations for nuclear power include: growing energy demand, concern overnational energy supply security, the increasingly volatile price of fossil fuels and global environmentalconcerns. The drivers appear to be the same for countries expanding existing nuclear programmes andthose seeking to introduce programmes. The projections made by different international organizationsindicate a significant growth in the use of nuclear power. The IAEA's projections indicate a world totalfor nuclear electrical generating capacity of between 445 and 543 GW(e) by 2020 and between 511 and807 GW(e) by 2030. This paper takes a detailed look into the global status of nuclear power, highlightingchallenges and prospects of the technology going into the next century.

Keywords: IAEA, nuclear power, global status

18 Invited Lectures

8111 INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEL!.. •:HR10Q0021..

IL-02

2020/2050 Perspectives for NuclearEnergy in the EU

CHRISTIANKlRCHSTEIGER

European Commission,Directorate-General for Energy,Directorate for Nuclear EnergyEUFO 04/295, L-2557Luxembourgchristian.kirchsteiger@ec.europa.eu

The objective of this presentation is to highlight the current and potentialfuture roles of nuclear energy in achieving the goals of the EU 2020/2050energy and climate policy.

The relation between the achievement of these goals and the needs forfurther decarbonisation of energy supply is evaluated in a 2050 perspec-tive. It is shown that the real issue is to strive for cost-effectiveness of solu-tions, involving both decarbonisation and efficiency measures.

High shares of low-carbon electricity can be achieved in the EU by 2050without unreasonable costs while limiting fossil fuel dependency by ap-plying on the demand side measures related to energy efficiency, trans-

port, co-generation, and on the supply side measures related to the use of aH low carbon options, i.e.renewables, nuclear power plants, CCS and CO2 efficient fossil fuels.

Renewable energy and energy efficiency measures are by no means sufficient to substitute for a phasingout of nuclear power plants.

In contrary, in order to achieve a sustained and secure electricity supply under the constraints of the EUenergy and climate policy goals, significant amounts of new nuclear generating capacity need to be de-ployed in Europe over the next few decades. An estimate of corresponding needs is given.

Finally, the European Commission s actions towards creating an EU-wide framework for a responsible useof nuclear energy are presented together with current trends on both EU and Member State levels.

Keywords: nuclear energy perspective, European Commision

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Invited Lectures 19

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M.*i.U;\rtO "" " -UJ£ IL-03I

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New Croatian Energy Strategy - Towardssustainable energy

NATAŠA VujEC The Republic of Croatia has been building the Krško Nuclear Power PlantState Secretary for Energy and a n ^ is participating in all the activities necessary for a successful operat-Mining ing of the plant now for almost thirty years. However, in the light of theMinistry of Economy, Labour nuclear energy renaissance it is necessary to prepare ourselves for newand Entrepreneurship challenges, stricter criteria of safety and protection, respect the indispens-Republic of Croatia ability of continuous re-examination of safety of procedures and methods.Ulica grada Vukovara 78 The Republic of Croatia has strictly committed herself to the nuclear en-10 000 Zagreb, Croatia e r gy prOgramme development - CRONEP in accordance with the meth-natasa.vujec@mingorp.hr odology of the International Atomic Energy Agency. Certainly, in the first

moment till the possible decision on the building of nuclear power plant,it will be necessary to make an institutional framework and create human resources and such an infra-structure that will be able to, when the decision will be taken, support the project and realize it withmaximal efficiency. We consider it the unique way in which it is possible to avoid what proved to be theweakness of some projects of nuclear power plants, that is missing a deadline and problems concerningfinancing that are intolerable taking into account the value of the investment. Likewise, since the Confer-ence is dedicated to small and medium-sized electric networks or to small nuclear power programmes,it needs to be mentioned that except the largest facilities it should be promoted researching of nuclearpower reactors of medium size whose development somehow falls behind in this moment Medium sizereactors gives great advantages to smaller economies in technical and financial sense.

From the current standpoint solutions of viability of nuclear programmes through re-processing of thespent nuclear fuel in new generation of power plants are discernible. Since today s technologies aresufficiently safe there is no need to wait with this development and fuel from one generation shall be re-processed into the fuel for the next generation of reactors. In the case of this closed fuel cycle, nuclearfuel reserves will be sufficient for some millennia. Therefore, in the European strategic technology planthe development of nuclear technology is included as one of seven areas of energy industry developmentto achieve deployment of cost-effective low carbon technologies.

Instead of conclusion I would like to point out that only if nuclear power is used in a safe, technicallyjustifiable and moral way it may become available to all and be a good answer to energy challenges of themodern world. Therefore it is necessary that each national nuclear energy programme has its full cred-ibility.

Keywords: energy strategy, Croatia, nuclear energy, sustainable

Invited Lectures

8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM i ' M ' - H R l 0 0 0 0 2 3 ; , ;-;

IL-04

Nuclear Liability, State of the Art

SEBASTIAAN M. S.REITSMA

Swiss Nuclear Insurance PoolMythenquai, 50/60, 8022Zurich, Swtizerlandsebastiaan_reitsma@swissre.com

Over fifty years ago states started to introduce legislation protecting thepublic against the potential magnitude and peculiarity of risks arisingfrom the nuclear energy production. They did so trough a specific liabil-ity and compensation regime. Whether legislation was based on nationalinitiatives or, as more frequently, related to international nuclear liabilityconventions, it was based on a number of principles being applied uni-versally. Furthermore, it at the same time strived for not preventing thedevelopment of the nuclear industry because of an unbearable liability.

This paper aims at explaining the broad outline of the above legislation, its development since its earlyyears, the state of the art as regards its modernisation as well as the (alleged) problems underlying thedelay in its introduction in a number of countries. When dealing with those problems it will be inevitableto touch upon a number of insurance related matters, which, as an insurer I am happy to tell, will lead meto familiar territory.

Keywords: nuclear energy production, liability and compensation regime, international nuclear liabilityconventions, insurance

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Invited Lectures 21

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSOU

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Session 1Energy Planning and Nuclear Option (EPNO)

° S l - 1 2 L. LlTVINSKY, O. PURTOV, V. BRONNIKOV, N. VLASENKO, S. SlLCHENKO

5 Concept of State Target Economic Program for Nuclear EnergyDevelopment up to 2020 23

Sl-40 N. ČAVLINA, D. RAŠETA, J. LEBEGNER

Prediction of Levelized Costs of New Nuclear, Gas and CoalPower Plants 25

Si-41 J. BAURSKI

Nuclear Co-Generating Plants for Powering and Heating toCleaning the Warsaw's Environment 26

S1-69 Ž. TOMŠIĆ, R. PAŠIČKO

CO2, Coal, and Gas Price Impacts on Nuclear Power PlantCompetitiveness in Croatia 27

S1-80 V. KNAPP, D. PEVEC, M. MATIJEVIĆ

On the Potential of Nuclear Fission Energy for Effective Reductionof Carbon Emission under the Constraint of Uranium ResourcesUse without Spent Fuel Reprocessing 28

S1-90 I. ANDROČEC, A. ĆURKOVIĆ, T. TARNIK

Power Generation Strategy Development in Croatia 29S1-99 I. JAKIĆ, J. LEBEGNER, N. PEROVIĆ

Programme of Preparatory Activities on Launching First NuclearPower Plant in Croatia 31

22

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ,.,.HR1000024.

Sl-12

Concept of State Target Economic Program forNuclear Energy Development up to 2020

L. LlTVINSKY, O. PURTOVState scientific - engineeringcenter of control systems andemergency response (SSECCSER),Pr. Geroev Stalingrada, 64/56,Kiev, 04213, UkraineLitvinsky@dnic.kiev.ua;Purtov@dnic.kiev.ua

V. BRONNIKOV

"Atomprojectengineering" ofNNEGC "ENERGOATOM"Gaidara st. 6, Kiev, 01033,Ukrainebronnikov@atom.gov.ua

N. VLASENKO,S. SlLCHENKOScientific Technical Center ofNNEGC "ENERGOATOM"Bogdana Khmelnitskogo st.63A, Kiev, 01054,Ukrainevlasenko@ntc.atom.gov.ua,Silchenko@ntc.atom.gov.ua

The purpose of the state target economic program of nuclear energy de-velopment till the year 2020 is keeping of power safety, improvement ofpopulation life quality and increase of national economy competitivenessdue to effective and competitive manufacture of electricity and thermalpower by nuclear power complex (NPC) of Ukraine in the volumes stipu-lated in the document "Energy Strategy of Ukraine till 2030"

Energy strategy foresees uniform power units for new site. On the newNPP sites construction of pressurized water reactors (WWER/PWR ac-cording to the IAEA classification) of pressurizeed heawy water reactors(PHWR) is possible.

Fullfilement of nuclear power complex parameters planned by EnergyStrategy is analysed with presumption of the preservation of existing levelof domestic infrastructure maintenance, as well as with the presumptionof its full scale development. Four sceanarios were analysed:

Scenario 1. Full-scale development of NPC domestic infrastructure, de-velopment of national nuclear power unit designs in cooperation withworld developers of light and heavy water reactor installations, expansionof new nuclear capacities construction under these designs by developeddomestic infrastructure and light water reactor (WWER/PWR) unitscommissioned till 2020;

Secanario 2. Full-scale development of NPC domestic infrastructure, de-velopment of national nuclear power units designs in cooperation withworld developers of light and heavy water reactor installations, expansionof new nuclear capacities construction under these designs by developed

domestic infrastructure and heavy water reactor (PHWR) units commissioned till 2020;

Secanario 3. Preservation of existing level of NPC domestic infrastructure, definition of foreign reactorunit suppliers based on the results of international tenders for each new NPP, expansion of new nuclearcapacities construction with light and heavy water reactor installations including involvement of availabledomestic infrastructure and light water reactor (WWER/PWR) units commissioned till 2020;

Secanario 4. Preservation of existing level of NPC domestic infrastructure, definition of foreign reactorunit suppliers based on the results of international tenders for each new NPP, expansion of new nuclear

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SESSION 1: Energy Planning and Nuclear Option (EPNO) 23

.2 8IH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSO

Ucapacities construction with heavy water including involvement of available domestic infrastructure andheavy water reactor (PHWR) units commissioned till 2020.

Keywords: energy strategy, state target economic program, nuclear power complex, WWER, PWR, PHWR

SESSION 1: Energy Planning and Nuclear Option (EPNO)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDiU" ".} X. ,^9P-.-.Yo- ; ^

SI-40

Prediction of Levelized Costs of New Nuclear,Gas and Coal Power Plants

NIKOLA ČAVLINA,DAVOR RAŠETAUniversity of Zagreb, Facultyof Electrical Engineering andComputingUnska 3,10000 Zagreb, Croatianikola.cavlina@fer.hr,davor.raseta@fer.hr

JOSIP LEBEGNERHrvatska elektroprivreda d.d.Ulica grada Vukovara 37,10000 Zagreb, Croatiajosip.lebegner@hep.hr

This article compares predicted costs of new base-load power plants. Costsare calculated as Levelized Unit Electricity Cost (LUEC). Power plants se-lected for comparison are coal-fired power plant, gas-fired power plantand nuclear power plant. Power plants powered by renewable sources arenot selected for comparison, because they cannot be relied upon to oper-ate as base-load power plants.LUEC for nuclear power plant includes decommission costs and spentfuel disposal costs. For coal-fired and gas-fired power plant LUEC in-cludes emissions fee for CO2. Foreseen prices of fossil-fuel fired powerplants with Carbon Capture and Storage (CCS) system installed are alsoincluded in comparison.Parameters needed for LUEC calculation are indentified and standard in-ternationally accepted LUEC methodology is used.Sensitivity study is performed, to determine the influence of most impor-

tant parameters (overnight cost, fuel cost, CO2 emission fees, cost of capital) on levelized costs of selectedpower plants.

Keywords: LUEC, nuclear, gas, coal, economy

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SESSION 1: Energy Planning and Nuclear Option (EPNO) <J r

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME Ol'JY: LukiRi t9P-QQ?§rt .

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Sl-41

Nuclear Co-Generating Plants for Powering and Heatingto Cleaning the Warsaw's Environment

JACEK BAURSKI In 2009 the Polish Government made a decision to introduce nuclearEconomic Society power to Poland. Two nuclear power plants (NPPs) will be constructedPolish Power Plants nearly at the same time - the first unit should start operation in 2020, and6-14 Krucza Str. by 2030 there should be about 6000 MWe added to the national electrical00-950 Warszawa, Poland grid. The Commissioner of the Government was nominated to introducejbaurski@energoprojekt.pl the Polish Nuclear Power Program (PNPP). One of the four vertically in-

tegrated - the biggest energy company (PGE - the Polish Energy Groupwith headquarters in Warsaw) was appointed to prepare investments.

These activities are planned in four stages:

I. up to 31.12.2010 - The PNPP will be prepared and the program must then be accepted by theGovernment.

II. 2011 - 2013 - Sites will be determined, and the contract for construction of the first NPP willbe closed.

III. 2014 - 2015 - Technical specifications will be prepared and accepted according the law.

IV. 2016 - 2020 - The first NPP in Poland will be constructed.

At present, the Government is receiving proposals from some regions of Poland asking that they be cho-sen for the NPP.

One of the obvious locations for the NPP is a 40-kilometer vicinity of Warsaw (1.8 mln inhabitants). Theneed for both electric power and heat is increasing because of the rapidly growing town. It gives the ex-tremely valuable chance for a very high thermodynamic efficiency of 80% in co-generation instead of 33%(max 36% for EPR-1600) for NPP generated electric power only. The Warsaw heating system has a capac-ity of 3950 MWt and is the biggest among EU countries. It is the third biggest in the world. Two NPPs,each of 2 x 1000 MWe could be built on the Vistula River up and down the town.

In 2005, UE calculated losses caused by gas emissions at 24 mid euro, and the span of human lives was sixmonths shorter in western countries and 8 months shorter in Poland. Warsaw's atmosphere is very pol-luted also because there are four heat and power generating plants: three coal and one oil -fired. In theseplants 3.5 million tons of hard coal is burned annually.

In conclusion, nuclear power for Warsaw is a very good solution for the delivery of electricity and heat inan environmentally responsible - zero emission - way.

Keywords: cogeneration, nuclear, Warsaw, environment

SESSION 1: Energy Planning and Nuclear Option (EPNO)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MF M *,\; i H R 1 0 0 0 0 2 7 ,

Sl-69

CO2 Price Impacts on Nuclear Power PlantCompetitiveness in Croatia

ŽELJKO TOMŠIĆUniversity of Zagreb, Facultyof Electrical Engineering andComputingUnska 3,10000 Zagreb, Croatiazeljko.tomsic@fer.hr

ROBERT PAŠIČKO

UNDP CroatiaRadnička 41,10000 Zagreb,CroatiaRobert.pasicko@undp.org

Long term power system planning faces growing number of concerns anduncertainties, which is especially true for nuclear power plants due to theirhigh investment costs and financial risk. In order to analyze competitive-ness of nuclear power plants and optimize energy mix, existing models arenot sufficient anymore and planners need to think differently in order toface these challenges. Croatia will join EU ETS (European Emission Trad-ing Scheme) with accession to EU (probably in 2012). Thus, for Croatianelectrical system it is very important to analyze possible impacts of CO2

emissions.Analysis presented in this paper is done by electricity market simulationmodel PLEXOS which was used for modelling Croatian electrical systemduring development of the Croatian Energy Strategy in 2008.

Paper analyzes impacts of CO2 price on competitiveness of nuclear power plant within Croatian powersystem between 2020 and 2025. Analyses are focused on how nuclear power plant influences total emis-sion from the power system regarding coal and gas prices, average electricity price regarding CO2, coaland gas prices price. Results of this paper are showing that with emissions from Energy strategy develop-ment scenario with two new coal power plants (600 MW each) and two new gas power plants (400 MWeach) until 2020, Croatia does not meet Kyoto target due to this emissions from power system. On theother side, introduction of nuclear power plants presented in this paper (1000 MW instead of one coaland one gas power plant) means nearly 6.5 Mt CO2 emissions less annually and gives possibility to achieveKyoto target (as this reduced amount represents nearly 22% of Croatian Kyoto target). Results are alsoshowing how increase in CO2 price is enhancing competitiveness of a nuclear power plant.

Keywords: power system planning, nuclear power plant, marginal costs, electricity market simulation,emission trading

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SESSION 1: Energy Planning and Nuclear Option (EPNO) <yi

.2 8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ML,/Hi .' f.i ^^1:P.PP,028 ; s

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Sl-80

On the Potential of Nuclear Fission Energy for Effective Reductionof Carbon Emission under the Constraint of Uranium Resources Usewithout Spent Fuel Reprocessing

*> VLADIMIR KNAPP, Urgency to stop further increase of greenhouse gases emissions and re-DUBRAVKO PEVEC, verse the trends, as stated in the Fourth Intergovernmental Panel on Cli-M A R I O M A T I J E V I Ć mate Change (IPPC) Report and in Copenhagen discussions, limits theUniversity of Zagreb, Faculty realistic choice of energy technologies to those available now or in theof Electrical Engineering and near future of few decades. In the coming fifty years neither nuclear fusionComputing nor carbon capture and storage (CCS) can be expected to give a signifi-Department of Applied cant contribution to world energy production. Two perspective intermit-Physics, University of Zagreb, tent sources such as wind and solar together with nuclear fission energyUnska 3,10000 Zagreb, covering the base load consumption appears to be a combination with aCroatia potential to produce a large share of carbon free energy in the total worldvladimir.knapp@fer.hr, energy production. This contribution considers the issues, associated

av o.pevecc • . w j t ^ r e q U j r e < j j a r g e s c a i e deployment of nuclear fission energy. A seriousmario.matiievic@rer.hr n , , i , , r • „ ,

question associated with nuclear energy is nuclear proliferation. Spreadof uranium enrichment and spent fuel reprocessing installations in many

new countries constructing nuclear reactors would be a major concern in present political environment.We investigate whether uranium resources would be sufficient to support nuclear build-up in next 50-60years sufficiently large to significantly reduce carbon emission without reprocessing of spent nuclear fuel.A positive answer would mean that 50-60 years can be available to develop effective international controlof nuclear fuel cycle installations. Our results show that a maximum nuclear build-up which would con-sume currently estimated uranium resources by 2065 without reprocessing could reduce by 2065 carbonemission by 39.6% of the total reduction needed to bring the WEO 2009 Reference Scenario prediction oftotal GHG emissions in 2065 to the level of the WEO 450 Scenario limiting global temperature increaseto 2 °C. The less demanding strategy of the nuclear replacement of all non-CCS coal power plants retiringduring the 2025-2065 period would reduce emission by 26.1%.Keywords: climate change, uranium resources, nuclear proliferation.

JO SESSION1: Energy Planning and Nuclear Option (EPNO)

; HR10nn02Q8™ I N T E R N A T I O N A L C O N F E R E N C E : N U C L E A R O P T I O N IN C O U N T R I E S W I T H S M A L L A N D M E i » ' . ' .,' i-1 • • ?-i . •• •

51-90too

Power Generation Strategy Development |in Croatia °

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A N T E C U R K O V I Ć , Electricity generation as an economic sector contributes to the national | .IVAN A N D R O Č E C , GDP through increasing investments and exports. In the period fromTAMARA TARNIK 2000 to 2008 the annual growth rate of final electricity demand was 3,8%Hrvatska elektroprivreda d.d. which was higher than for any other energy form. Almost 1200 MW ofUlica grada Vukovara 37, thermal power plants will go out of system due to lifetime (more than 3010000 Zagreb, Croatia years).ante.curkovic@hep.hr, Energy Strategy is a basic document of the Energy Act with the purpose toivan.androcec@hep.hr, d e f i n e e n e r g y p o l i c y a n d f u t u r e p , a n s for e n e r g y development of the Re-tamara.tarnik@hep.hr p u b | i c o f C r o a t i a t i]j 2 0 20. Based on the adopted strategy the Government

will create the Energy Strategy Implementation Programme for the four-year period. Croatia's energy development should be based on best available technologies as well as onenergy-related, economic and environmental assessment of all available energy options. Energy strategyof Croatia (NN 130/09) puts up next goals: 300 MW hydro power plants (>10 MW), 1200 MW gas-firedthermal power plants (including 300 MW of cogeneration), 1200 MW of coal-fired thermal power plants,and 35% of renewables (including hydro).The market, i.e. a competitive generation, is the driving force in the construction of new power plants.The main stimulus for the construction is the possibility of definite return of invested capital as well asearning of reasonable profit for investors. Choose of location, environmental impact and competitivenessare main criteria for decision making. Technological and financial terms of new power plant is under in-fluence of the law of supply and demand, so short marginal costs are in the first view - power plant life isat least 30 years - how to deal with this conditions, who will invest in long-term projects with conditionof short pay-back period.

Climate change and greenhouse gas emissions have become a priority development issue. The main chal-lenge is a long-term development of economy with decreased emission of carbon dioxide. Kyoto protocolobligations, Copenhagen Accord and EU emission trading scheme are setting development goals regard-ing CO2.In 2013-2020 (EU ETS III) all thermal power plants should buy 100% emission allowances on auction.Implementing Croatian energy strategy, power sector will need extra 7,5-8,5 mil t of CO2 for 2020 (con-sumption 28 TWh) in comparison with 2005 (consumption 17 TWh) or in total 12-13 mil t CO2. withpresumed price of 40 €/t CO2 Croatian power sector will have extra cost of around 500 mil € annually.Minimum 50% of those fund necessary for buying 4,5 mil t will be some national fund and half of the rest

SESSION 1: Energy Planning and Nuclear Option (EPNO) <1 (

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSIU.* of fund till 12 mil t will be fund of some EU Member State. If we are not able to buy extra emission, we will> need to import the electricity. In very conservative scenario we can presume that Croatia will not be able-§ to import the electricity and than we need to include costs of VOLL which are minimally 4 €/kWh.o- So, the greatest problem today is climate change on the one hand and security of supply on the other. Ofg all the observed measures, nuclear energy use is the measure with the greatest potential in decreasing the& greenhouse gas emissions. Secondly, nuclear energy contributes to security of supply because it increaseso the variety of energy sources. However, all aspects of the environmental impact, especially with regard toi decommissioning and radioactive waste disposal should be considered. Nuclear option is only solution

^ for economy of Croatia.

Keywords: power system, development, generation, nuclear option

SESSION 1: Energy Planning and Nuclear Option (EPNO)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND Mi -?HU.\: :'.i ̂ < ? R 9 ; i , V.'1.^

Sl-99

Programme of Preparatory Activities on LaunchingFirst Nuclear Power Plant in Croatia

IRENA JAKIĆ,JOSIP LEBEGNER

Hrvatska elektroprivreda d.d.Avenija grada Vukovara 37,10000, Zagreb, Croatiairena.jakic@hep.hr,josip.lebegner@hep.hr

N I N O PEROVIĆproMCon GmbHSandstrasse 33, 5412Gebenstorf, Switzerlandnino.perovic@promcon.ch

New Croatian energy policy recognizes nuclear energy as solution for ris-ing needs for energy and, thus, opens the possibility to construct first nu-clear power plant in Croatia. Within this frame, the Croatian governmentis developing an implementation programme according to this policy andpreparing basis for making decision about construction of nuclear powerplant. Croatian parliament is responsible for this decision which is ex-pected by the end of 2012. During this period, stakeholders in this proj-ect (government, regulatory body and future operator of the plant) haveto complete activities of preparatory phase of Croatian Nuclear EnergyProgramme (CRONEP) project according to methodology recommendedby IAEA (International Atomic Energy Agency). This paper defines theseactivities and estimate the costs of first, preparatory phase based on previ-ous experience of other countries which finished the phase successfully.Also, it describes the potential role of Croatian utility as stakeholder due

to its experience as co-owner of Nuclear power plant Krško

Keywords: energy policy, first nuclear power plant, Croatian Nuclear Energy Programme

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SESSION 1: Energy Planning and Nuclear Option (EPNO) 31

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSoU

Session 2c22

o

Power Reactors and Technologies (PRT)

° S2-IL-117 Z. V. STOŠIĆ

« On the Matter ofNPP New Builds 33S2-IL-23 P. GAIO

Westinghouse API000: Leading the Nuclear Renaissance 34S2-11 J. B. MALHERBE, C. E. CLOETE

The South African Pebble Bed Modular Reactor and Its Implicationsfor Residential Power Consumption in Developing Countries 35

S2-39 N. M. S. BERGROTH

Large-Scale Combined Heat and Power (CHP) Generation atLoviisa Nuclear Power Plant Unit 3 36

S2-52 B. PETROVIC, K. BURN, M. CIOTTI, F. FRANCESCHINI, L. CASALINI,M. SAROTTO, M. CARELLI, J. SEJVAR, C. LOMBARDI, JEFF JOHNSON,JORDAN MCKILLOP, D. HARTMANGRUBER

Design Features of the IRIS Reactor to Reduce Collective Doseduring Operation and Maintenance and to Simplify D&D 37

S2-60 Y. N. KUZNETSOV

Nuclear Co-Generation Desalination Complex with VK-300Simplified Boiling Water Reactor 39

SESSION 2: Power Reactors and Technologies (PRT)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEC5U.\. •

S2-IL-117

On the Matter of NPP New Builds

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QZORAN V. S T O Š I Ć In the past decades the nuclear option has developed to become a mea- QDirector R&D Installed s u r e to secure the energy supply not only of the established nuclear na-Base Engineering tions, but also of newly embarking or smaller countries without signifi-Director Marketing & Sales cant nuclear experience. In these small countries cooperation may workEx-Yugoslavia cross-border between countries or cross-corporate between manufac-AREVA NP GmbH t u r e r s and/or utilities.

° e s n ' ~ Since the time span between decision-making for building, the licensing. procedure, the detailed planning, the construction phase and commis-

zoran.stosic@areva.com r . r D \sionmg can amount to 10-15 (and even more) years, this leads to the pub-lic discussions and urgent requirements of having to incorporate the con-

stant experience gained on all technical, administrative (regulatory and authorities) and political (govern-mental) levels. This has to be taken into account for the safety-related boundary conditions in the frameof a new build project. Often neglected is the fact that this also applies to the choice of the guidelines toput into effect, to an efficient and competent authority and utility body and the integration of adequatetechnical specialists. Utilities face different requirements depending on whether they are situated in thecountry of responsible nuclear power plant utilities' headquarters or whether they are merely co-ownersof a foreign plant. All these matters profit from resorting to the knowledge pool from operational experi-ences and experiences gained in new build projects.Regarding a new build project the milestones in the development of a national nuclear power infrastruc-ture as well as involvement of the main local (national) organizations and progressive application of theIAEA safety requirements are presented. Workforce planning during construction and operation includ-ing educational needs is shown for a single country example. A breakdown of total contract amount andactivity itemization is given. Aspects of a new build project are discussed for two typical examples:« New Build Plan - starting with decision making process, performing feasibility studies, checking

timeline and analyzing challenges including effects on economy;

• New Build Construction - giving the context, major achievements and general site work status.

Keywords: nuclear option, new builds, NPP

SESSION 2: Power Reactors and Technologies (PRT) o O>

HR1000032.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND^E.O;; TM hi.^C 1 A :.,. !Y U(:US

n ' • - - . . . .oU* S2-IL-23cIQ

o

Westinghouse AP1000:Leading the Nuclear Renaissance

PAOLO G A I O The distinguished features of AP1000 passive safety technology are high-Westinghouse Electric lighted. In particular the AP1000 safety features are described as well asCompany their implications for simplifying the design, construction and operationRue Montoyer 10,1000 of this design compared to currently operating plants and how the plantBruxelles, Belgium represents a breakthrough in the nuclear energy sector. The modular con-gaiop@westinghouse.com struction concept application is also explained and how the simplification

and organization of site and factory activities reduces the constructionschedule while increasing the quality.

Finally the status of construction activities of the four AP1000 construction in China and six US is de-scribed including pictures and construction animations.

Keywords: passive safety, modular construction, China projects

JA SESSION 2: Power Reactors and Technologies (PRT)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME!WJ.Vi [. . H R 1 0 , 0 0 0 3 3 ; •

S2-11

The South African Pebble Bed Modular Reactor and Its Implicationsfor Residential Power Consumption in Developing Countries

JOHAN B. MALHERBECHRIS E. CLOETE

Department of PhysicsDepartment of ConstructionEconomicsUniversity of PretoriaPretoria, 0002, South Africajohan.malherbe@up.ac.zachris.cloete@up.ac.za

From an analysis of world energy consumption trends and the Kyoto Pro-tocol it is clear that the contribution of nuclear power as well as other re-newable energy technologies will have to be increased in the near future.The main problem of nuclear power plants is the production and longterm storage of radioactive waste products. The Pebble Bed Modular Re-actor (PBMR) is a radically new design in nuclear power reactors. Some ofthe salient features of the South African PBMR design will be described.Because the PBMR is a small reactor (typically 200-400 MW) and inher-ently safe, it is suitable for local electrical power supply to small cities orlarge housing schemes in developing countries. Implications for the latterare discussed.

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Keywords: nuclear reactor, HTR, nuclear waste management, residential power

SESSION 2: Power Reactors and Technologies (PRT)

.3 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MKfJIU.VI V.« .

5c>o

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S2-39

Large-Scale Combined Heat and Power (CHP) Generationat Loviisa Nuclear Power Plant Unit 3

NlCi BERGROTH Fortum has applied for a Decision in Principle concerning the construc-Fortum Power and Heat, Power t i ° n °f a n e w nuclear power plant unit (Loviisa 3) ranging from 2800-4600Division, Loviisa 3-project MWth at its Loviisa site located at the southern coast of Finland. An attrac-P.O. Box 100, 00048 Fortum, tive alternative investigated is a co-generation plant designed for large-Finland scale district heat generation for the Helsinki metropolitan area that isnici.bergroth@fortum.com located approximately 75 km west of the Loviisa site. The starting point is

that the district heat generation capacity of Loviisa 3 unit would be around1 000 MW,h.

The possibility of generating district heat for the Helsinki metropolitan area by Loviisa's two existingnuclear power plant units was investigated back in the 1980s, but it proved unpractical at the time. Withthe growing concern of the climate change and the subsequent requirements on heat and power genera-tion, the idea is much more attractive today, when recognising its potential to decrease Finland's carbondioxide emissions significantly.

Currently the district heat generation in Helsinki metropolitan area is based on coal and natural gas,producing some five to seven million tonnes of carbon dioxide emissions annually. Large-scale combinedheat and power (CHP) generation at the Loviisa 3 unit could cut this figure by up to four million tonnes.This would decrease Finland's carbon dioxide emissions by as much as six percent. In addition, large-scale CHP generation would increase the overall efficiency of the new unit significantly and hence, reducethe environmental impact on the local marine environment by cutting heat discharges into the Gulf ofFinland.

Nuclear energy has been used for district heating in several countries both in dedicated nuclear heatingplants and in CHP generation plants. However, the heat generation capacity is usually rather limited,maximum being around 250 MWth per unit. Set against this, the Loviisa 3 CHP concept is much moreambitious, not only because of the much larger heat generation output envisaged, but also because thedistrict heating water would have to be transported over a rather long distance.

This paper describes the general concept of the Loviisa 3 CHP generation; it addresses the technical start-ing points as well as the general design and safety requirements with regard both to the co-generationplant and the district heat transport system. The use of APROS simulation software for preliminary safetyanalyses during the design phase is presented and discussed.

Keywords: combined heat and power, co-generation, CHP, district heat, Loviisa 3

SESSION 2: Power Reactors and Technologies (PRT)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEV:!U.\

Design Features of the IRIS Reactor to Reduce Collective Doseduring Operation and Maintenance and to Simplify D&D

S2-52

BO/AN PETROVIC

Nuclear and RadiologicalEngineering, Georgia Instituteof Technology770 State St., Atlanta, GA30332-0745, USABojan.Petrovic@gatech.edu

KENNETH W. BURN,MARCO CIOTTI,LODOVICO CASALINI,MASSIMO SAROTTO

ENEAVia Martiri di Monte Sole 4,40129 Bologna, ItalyKBurn@bologna.enea.it,Marco.Ciotti@frascatti.enea.it,Ludovico.Casalini@bologna.enea.it,Massimo.Sarotto@bologn.enea.it

F A U S T O F R A N C E S C H I N I ,

M A R I O C A R E L L I ,

JIM SEJVAR

Westinghouse Electric Company1344 Beulah Rd, Pittsburgh,PA 15235, USA

FranceF@westinghouse.com,CarellMD@westinghouse.com,SejvarJ@westinghouse.com

JEFFREY JOHNSON

Oak Ridge National LaboratoryMS 6170.P.O. Box 2008, OakRidge, TN 37831, USAJohnsonJO@ornl.gov

C A R L O L O M B A R D I

Politecnico di Milano,Dipartimento di IngegneriaNuclearevia Ponzio 34/3,20133 Milano, ItalyCarlo.Lombardi@fastwebnet.it

JORDAN MCKILLOPANDDAVID HARTMANGRUBER

Nuclear and RadiologicalEngineering, Georgia Instituteof Technology770 State St., Atlanta, GA30332-0745, USAJordan.McKillop@gatech.edu,DHartmangr3@gatech.edu

IRIS is an advanced PWR of integral typeand medium-level power output of 335MWe. Its design aims to improve perfor-mance of current LWR designs in severalkey areas. One of these areas is the radia-tion field at the plant and the potentialbenefits of its reduction on the collectivedose to personnel and on decommission-ing and dismantling (D&D) cost.

Specifically, significant reduction was tar-geted in reactor vessel fast neutron flu-ence, dose in accessible areas, activation ofcomponents outside reactor vessel, activa-tion of reactor vessel, and activation of theconcrete wall forming the reactor vesselcavity.

In pursuit of the above reduction, a coor-dinated effort was undertaken by severalgroups within the IRIS team, includingWestinghouse Electric Company LLC(USA), Agenzia nazionale per le nuovetecnologie, 1 energia e lo sviluppo econom-ico sostenibile - ENEA (Italy), Georgia In-stitute of Technology (USA), Politecnicodi Milano (Italy), and Oak Ridge NationalLaboratory (USA). Aggressive targets were

defined at the early stage of the IRIS project to enable accommodating any design change necessary tomeet the objectives in a timely fashion. Comprehensive analyses have been performed, and the objectiveshave been either confirmed or made possible by adequate design modifications.

All these design features ultimately result in cost savings and contribute to economic competitiveness ofIRIS. It should be noted that while the decommissioning is projected to occur not sooner than 60-100years into future, the utilities are typically required to accrue adequate financial resources for decom-

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SESSION 2: Power Reactors and Technologies (PRT) 'jn

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSIsoU.g missioning during the lifetime of the plant, e.g. by establishing a decommissioning fund. Therefore, the> decommissioning cost is not postponed but contributes to the current operating expenses, making any

•§ potential associated savings very tangible for the utility since it directly reduces the present cost of elec-Q. tricity.° Keywords: IRIS reactor, dose reduction, activation reduction, simplified maintenance and D&D

ocs

3 Q SESSION 2: Power Reactors and Technologies (PRT)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEu'l).-• - HR.10QOO36-.

S2-60

Nuclear Co-Generation Desalination Complex with VK-300Simplified Boiling Water Reactor

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YURY N. KUZNETSOV With regard for the global-scale development of desalination technologies QN.A. Dollezhal Research and a n c ' t n e stable growth demand for them, Russia also takes an active part |Development Institute of Power m the development of these technologies. Two major aspects play a spe- w

Engineering cial role here: they are providing the desalination process with power andP.O.Box. 101000, Moscow, introducing new materials capable to make the production of fresh waterRussia cheaper and raise the technical reliability of desalination units.kuz@nikiet.ru In achieving these tasks, the focus is on the most knowledge-intensive

issues, to which Russia is capable to make its contribution based both onthe experience of developing national nuclear power and the experience of developing, manufacturingand operating desalination units, including the use of nuclear power (the experience of BN-350 in Aktau(formerly Shevchenko), Kazakhstan.

In terms of design, Nuclear Desalination Complex (NDC) with VK-300 reactor facility is a modificationof a nuclear power unit with VK-300 reactor developed for application at Russian nuclear cogenerationplants. A power unit with VK-300 reactor has a design power of 250 MW(e) with the turbine unit opera-tion in the condensation mode. In modes with the heat supply for desalination needs, up to 400 Gcal/h ofthermal energy can be used as a steam from turbine extractions with the simultaneous electricity genera-tion by the turbine generator of about 150 MW.

The report considers a VK-300 reactor based NDC with MED based distillation desalination units withhorizontal-tube film evaporators. Russia has an extensive experience of commissioning and long-termcommercial operation of domestically built desalination units with horizontal-tube evaporators of differ-ent power (from 0.1 to 700 m3/h). Seawater desalination units built on their basis are more economic thanevaporators of other types - by the factor of 1.5-2.0 in terms of the energy consumption and by the factorof 1.5-1.8 in terms of the specific quantity of metal and the development area. With regard for the powerunit capabilities of supplying heat for desalination (200-400 Gcal/h) as part of an NDC with a VK-300, itis expedient to use distillation units with a higher unit capacity.

The most attractive option is coupling of the VK-300 energy source with distillation desalination unitsoperating based on the multi-stage evaporation principle (MED). This is the effective NDC structure al-lowing the use of turbine steam extractions for heat supply (via the intermediate circuit) to the desalina-tion system producing high-quality distillate. As it provides with thermal energy a desalination complexwith the capacity of 300.000 m3/day, a nuclear plant consisting of two VK-300 power units allows produc-tion of distillate with the cost of 0.58 dollars/m3. In this case, the electricity supply to the power system is357 MW(e). The electricity cost is 0.029 dollars/kWh.

Keywords: cogeneration, nuclear, desalination, BWR, VK-300

SESSION 2: Power Reactors and Technologies (PRT) o n

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSoU

4 Session 3

I

Nuclear Energy and Environment (NEE)

S3-20 I. PRLIĆ, M. SURIĆ MIHIĆ, G. MAROVIĆ, M. NOVAKOVIĆ,T. MEŠTROVIĆ, Z. CEROVAC

Total Occupational and Possible Public Member Exposureduring Characterisation, Conditioning and Securing ofRadioactive Sealed Sources - A New Dosimetric ConceptUsing Active Electronic Dosimeters 41

S3-22 I. PRLIĆ, G. MAROVIĆ, R. TURK, T. BITUH, M. SURIĆ MIHIĆ, B. SKOKO,T. MEŠTROVIĆ, E. SPITALER, Z. VUČIĆ

TENORM Characterisation, Conditioning and Remediationto be Reused in New Products and Associated Possible PublicMember and Occupational Hazard 42

S3-28 I. KODELI, G. GUALDRINI, S. AGOSTEO, D. BROGGIO, L. DE CARLAN,E. GARGIONI, J. M. GOMEZ-ROS, B. GROSSWENDT, C. HUET, R. PRICE,S. ROLLET, B. R. L. SIEBERT, L. STRUELENS, R. TANNER, H. VINCKE,B. WIEGEL, M. ZANKL

Activities of the EUR AD OS Working Group 6 onComputational Dosimetry 43

S3-88 M. MlHALINA, B. GLASER

Determination of Radiological Dilution Factors in the SavaRiver for new Reference Group of Inhabitants DownstreamoftheKrškoNPP 44

/ in SESSION 3: Nuclear Energy and Environment (NEE)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M E P ; v/r , . . r i H#.1000037

S3-20

Total Occupational and Possible Public Member Exposure duringCharacterisation, Conditioning and Securing of Radioactive SealedSources - A New Dosimetric Concept Using Active Electronic Dosimeters

Radiation dosimetry in protection against ionizing radiation involves re-search of all possible pathways through which natural or man-made radio-active materials can contaminate a habitat and actually harm its biota. Italso takes into account natural and artificial (man-made) electromagneticionizing radiation (y and x radiation). The purpose of conducted studywas to validate a new active electronic dosimeter (AED) of type ALARAOD and to develop a new monitoring method by tracing the possible ex-ternal occupational and/or public exposure over real time. This method isused to continuously measure and record external radiation doses. A nov-elty is, establishing dose rates receiving pattern as a function of real time.This article presents a dosimetric study assessing exposure to man-madeionizing radiation of local environment and total occupational exposureof two professional workers involved in characterization, conditioning,and securing of unused radioactive sealed sources. Occupational wholebody dosimetric results obtained with AED were compared with resultsobtained with passive dosimetry (film badge and thermoluminiscence).Air, dust, and silicon sand samples were analyzed by gamma-spectrome-try to estimate internal exposure of the two workers to 222Rn due to inhala-tion or ingestion of dust and sand in indoor air. In order to establish totaloccupational exposure, control radon measurement was performed in theimmediate environment. The set of quantities describing possible hazarddue to exposure of a public member to radionuclides with activity concen-trations contributing the LBG and the external and internal Hazard index(Hex, Hint) ware calculated and brought to discussion.

Keywords: AED, ALARA, effective dose, electronic dosimetry, hazard index, Hp(10), low level waste, per-sonal dosimetry, radiation protection, risk assessment

IVICA PRLIĆ,

MARIJA SURIĆ MIHIĆ,

GORDANA MAROVIĆ,

TOMISLAV MEŠTROVIĆ,

Institute for Medical Researchand Occupational HealthKsaverska cesta 2, 10000Zagreb, Republic of Croatiaiprlic@imi.hr,msuric@imi.hr,marovic@imi.hr,tomislav@imi.hr

M L A D E N N O V A K O V I Ć

Ekoteh dosimetry Ltd.Radiation Protection Co.Vladimira Ruždjaka 21,10000Zagreb, Republic of Croatiamnovakovic@ekoteh.hr

Z D R A V K O C E R O V A C

Alara Instruments LtdVeslačka 4,10000 Zagreb,Republic of Croatiazdravko@alara.hr

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SESSION 3: Nuclear Energy and Environment (NEE) 41

.3 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND Mć>7rt _oU

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TENORM Characterisation, Conditioning and Remediationto be Reused in New Products and Associated Possible PublicMember and Occupational Hazard

S3-22

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IVICA PRLIĆ,GORDANA MAROVIĆ,RAJKA TURK,TOMISLAV BITUH,MARIJA SURIĆ MIHIĆ,BOŽENA SKOKO,TOMISLAV MEŠTROVIĆ,Institute for Medical Researchand Occupational HealthKsaverska cesta 2,10000Zagreb, Republic of Croatiaiprlic@imi.hr,marovic@imi.hr,tbituh@imi.hr,msuric@imi.hr,bskoko@imi.hr,tomislav@imi.hr

EWALD SPITALERTechnisches Buero Spitaler,Grassnitz 50; 8624 Au beiAflenz, Republic Austriatbspitaler@t-online.at

ZLATKO VUČIĆInstitute for PhysicsBijenička 46, 10000 Zagreb,Republic of Croatiavucic@ifs.hr

If the TENORM is a byproduct originating from any energy gaining tech-nological production process is to be reused as a product - raw materialfor other advanced product it has to meet the ultimate condition regulatingthe content of NORM or TENORM material in a final product. It meansthat the minimum requirements to be achieved are to mix the TENORMmaterial with any other suitable material resulting in final H e x less thanunity (Hex<l) for any quantity of TENORM mixed. Despite of a presentlack of national legislation covering the use and handling of NORM andTENORM we can use the existing worldwide recommendations based onthorough radiological characterization. If the recommended UNSCEAR2000 limit values are used as a base for discussion demanding that theTENORM is to be mixed with other suitable materials and monitored be-fore further reuse as a constructing material product, especially construct-ing material for human housing, the listed quantities: Raeq HeXj D(nGy/h),H jni Iyr, Dind(mSv/ r), Dout(mSv/yr), Sampling site - GPS (coordinates ofTENORM samples) calculated from the measured dose rate and activ-ity concentration data will be the key quantities describing the radiologi-cal characterization of any TENORM facility. The reuse of TENORM ina new product is recommended (if economically cost-effective) but onlyunder the professional supervision of total radionuclide activity content infinal product. We are presenting the public hazard assessment procedureat phosphogypsum (PG) tailing facility as a specific TENORM site whichhas nothing in common with dangerous or hazardous RadWaste in thesense of the existing legal legislation, not EU nor national Croatian. TheEU and national legislation based on the definition of reference levels ofradio nuclides present in TENORM is in process and Article 35 of Eura-tom Treaty is in process to be taken into account in future.

Keywords: TENORM, radium index, radwaste, public health risk, hazard,dose limits

/VJ SESSION 3: Nuclear Energy and Environment (NEE)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ! U HR1QQ0P39 S

S3-28

Activities of the EURADOSWorking Group 6 onComputational Dosimetry

IVAN KODELI,1

G. GUALDRINI,2

STEFANO AGOSTEO,3

DAVID BROGGIO,4

LOIC LENOIR DE CARLAN,5

E. GARGIONI,6

J. M. GOMEZ-ROS,7

B. GROSSWENDT,8

CHRISTELLE HUET,4

R. PRICE,9

SOFIA ROLLET,10

B. R. L. SIEBERT,8

L. STRUELENS,"RICK TANNER,12

HELMUT VINCKE,13

BURKHARD WlEGEL,14

M. ZANKL 1 5

'IJS, Slovenia, 2ENEA, Italy;^Politecnico dl Milano,Italy; 4IRSN, France; "CEA,France; "University MedicalCenter Hamburg-Eppendorf,Germany; 7CIEMAT,Spain; "retired from PTB,Germany, 9City University,UK; "'AIT, Austria; "SCK-CEN, Belgium; I2HPA, UK;"CERN, Switzerland; "PTB,Germany,'*HMGU, Germany

ivan.kodeli@ijs.si,guald@bologna.enea.it,stefano.agosteo@polimi.it,david.broggio@irsn.fr,loic.lenoir-de-carlan@cea.fr,e.gargioni@uke.de,jm.gomezros@ciemat.es,bernd.grosswendt@ptb.de,christelle.huet@irsn.fr,r.price@city.ac.uk,sofia.rollet@arcs.ac.at,bernd.siebert@ptb.de,lstruele@sckcen.be,rick.tanner@hpa.org.uk,helmut.vincke@cern.ch,burkhard.wiegel@ptb.de,zankl@helmholtz-muenchen.de

The objective of EURADOS (EuropeanRadiation Dosimetry Group, www.eura-dos.org) is to stimulate collaboration be-tween European laboratories in the field ofdosimetry of ionising radiation, in particu-lar in the areas of radiation protection, ra-diobiology, radiation therapy and medicaldiagnosis. In this paper the activities of itsWorking Group 6 on Numerical Dosim-etry is presented.

The Working Group has now 15 full mem-bers, more than 20 corresponding mem-bers, and is still opened to newcomers.The group pursues two main aims:

(1) Coordination of research on and de-velopment of computational methodsin in radiation dosimetry and

(2) Support of education and training.

Keywords: dosimetry, benchmarks, training, uncertainty

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SESSION 3: Nuclear Energy and Environment (NEE) A o

HR1000040.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME Ji j / . ' T ! ~C t'i'AC'i V f-:K;:.:cto

ouž S3-88'5| Determination of Radiological Dilution Factors in the Sava River for3 new Reference Group of Inhabitants Downstream of the Krško NPPo

Ig M A R I O M I H A L I N A , Krško NPP occasionally conducts planned liquid radioactive effluent dis-J, BRUNO GLASER charges to the Sava river. Studies from the Institute "Jožef Stefan" in Lju-"" NPP Krško bljana (IJS) entitled "Exposure of Population due to Liquid Effluents from

Vrbina 12,8270 Krško, NPP Krško to the Sava River" assumes that radionuclides introduced toSlovenia the Sava river are uniformly dispersed through the river volume, and thatmario.mihalina@nek.si, fishing occurs far enough downstream from the point of discharge (suchbruno.glaser@nek.si as the Brezice and Jesenice regions) to obviate any measurable exposure.

However, due to recent incidents of fishing at the property limits of NPPKrško, it was deemed necessary to re-evaluate and re-calculate total dose,

as well as define a new dispersion coefficient for the new reference group, which was determined to in-clude fishing activities at approximately 350 m downstream of the Krško NPP river dam. Therefore, a newdilution factor was defined for the new reference group, and it is also (conservatively) assumed that fish-ing occurs in the mainstream flow having the highest concentration of radionuclides, prior to dispersionin the river volume as referenced above.The Institute "Ruder Bošković" (IRB) in Zagreb, Croatia, has made subsequent measurements of radio-nuclide tritium concentration and dispersion flow during Waste Monitor Tanks (WMT) discharge as theSava River flows downstream through Zagreb and Croatia. On analysis of their results, along with ourown research into mainstream flows, it was possible to better define the dilution factor for most of theaffected flow area.In the most affected mainstream flow area, about 350 m downstream of NPP, it is expected that a valueof approximately 50% concentration would be measured at the NPP river dam, which is three times theradionuclide activity measured at the Brezice (Slovenia) radioactivity monitoring station further down-stream. Analysis also shows that fishing positions from both sides of the river in the vicinity of the NPPare generally not affected by the maximum concentration assumed to be in the mainstream EssentialService Water (ESW) discharge flows (which is concentrated in the middle of the river flow). In specificconditions of fishing, these locations may be even less affected than the reference group fishing in riverradionuclide dispersion areas (such as the Brezice and Jesenice locations further downstream).Further studies and measurements on location made by IJS had confirmed results from this report. Re-sults for annual exposure of critical groups and the most exposed individual in Slovenia and Croatiashows that even with most conservative approach and extreme NPP effluent discharge, the received dosesare negligible

Keywords: radiological dilution factor, NPP Krško, Sava river

ti A SESSION 3: Nuclear Energy and Environment (NEE)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS

Session 4Operation and Maintenance Experience (OME)

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S3O

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§S4-14 P. LOVRENČIČ, D. KAVŠEK Q

New Fire Protection Inspection Technique 47 £

S4-34 D. CicvARićIntegration of the Ovation Based Distributed Turbine ControlSystem into the Existing Process Information System and FullScope Simulator at NPP Krško 48

S4-56 P. BUDULAN

Successful Operation of the Only CANDU Type Reactorin Europe 49

S4-76 M. PAJNIĆ, H. FRANJIĆ, G. SMOLJKIĆ, K. MARKULIN, A. VUČAJNK, F. JARNJAK

Advanced Approach of Reactor Pressure Vessel Head Inspectionand Repair of CRDM J-Weld 50

S4-77 M. PAJNIĆ, A. MATOKOVIĆ, K. MARKULIN, H. FRANJIĆ

Advanced Approach of Reactor Pressure Vessel In-ServiceInspection 51

S4-78 M. PAJNIĆ, S. GALOŠIĆ, H. FRANJIĆ, K. MARKULIN

System for Eddy Current Inspection of WER-440/1000 SG's Tubes 52

S4-81 I. KUZLE, D. BOŠNJAK, H. PANDŽIĆ

Auxiliary System Load Schemes in Large Thermal and NuclearPower Plants 53

S4-87 T. BAJS, M. BALIĆ, I. BAŠIĆ, I. VRBANIĆ, B. SEMBER, N. DJETELIĆ

NPP Krško Approach to Pressure Locking and Thermal Binding inMotor Operated Valves 54

S4-89 M. MIHALINA, N. DJETELIĆ

Component Cooling Heat Exchanger Heat Transfer CapabilityOperability Monitoring 55

SESSION 4: Operation and Maintenance Experience (OME) AC

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSo

UŽ S4-96 P. SCHIMANNcg Requirements and Possibilites for Operational Experience£ Feedback from the Plant's Manufacturer's Point of View 560 S4-98 F. JARNJAK, S. REŠKOVIĆ, E. PICEK3

oCN

Next Generation of ECT Software for Data Analysiso of Steam Generator Tubes 57CN

S4-102 D. MANDIĆ, M. J. ZILAVY

Turbine Control System Replacement at NPP NEK; SystemSpecifics, Project Experience and Lessons Learned 58

S4-107 M. VAVROUŠ, R. GRACIN

Qualification Practices in Nuclear Industry: Steam GeneratorEddy Current Probe Qualification 60

S4-113 M. DUDAŠ

Automation of Shift Work in Operations 61

S4-115 Z. BERTALANIĆ, M. PAVLICA, Z. MALJKOVIĆ

High Partial Discharge Levels in Nuclear Power PlantTurbo-Generator 62

SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME<.)!',\\; VI A71 "A1,

S4-14

New Fire Protection InspectionTechnique

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PETER LOVRENČIČ, The Fire Protection system being one of the most important safety systems QDARKO KAVŠEK in a Nuclear Power Plant needs to be fully operational and reliable. The |NPP Krško system is mostly made of carbon pipes and valves, filled with water, whichVrbina 12, KRŠKO 8270, i s n o < : subject to any special chemistry treatment. However, it is most vul-Slovenija nerable to corrosion - a very important degradation mechanism, whichpeter.lovrencic@nek.si, behaves unpredictable. Since the system is also one of the biggest systemsdarko.kavsek@nek.si in the plant, it is difficult to predict the exact location of the defect. The

best known preventive action is inspection but unfortunately, it is impos-sible to inspect the whole system with a classic Ultrasonic Technique. In recent years, computer-assistedinspection techniques have improved significantly. Other industries, e.g. petroleum industry started toapply a very effective tool called Guided Waves for permanent corrosion monitoring of large portionsof straight carbon pipes under insulation. At KRŠKO NPP, we applied this technique to inspect the FireProtection pipes. The results have met our expectations. Following an overview of pipe condition, the in-spection results showed parts of pipes, some of which will have to be either closely monitored or replacedin the future. The new inspection technique can increase the system's reliability and therefore might beapplied as the standard inspection technique for Fire Protection system Inspection Program.

Keywords: ultrasonic inspection, guided waves

SESSION 4: Operation and Maintenance Experience (OME) AH

.2 81H INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND .vll-JJi^.Vi)";.('7 XX.Y \ tJliiD.Sn2 •u

cI•§Qocs

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S4-34

Integration of the Ovation Based Distributed Turbine ControlSystem into the Existing Process Information System and FullScope Simulator at NPP Krško

DARKO CICVARIC Programmable Digital Electro Hydraulic System (PDEH) is Turbine Con-NPP Krško t r o ' System (TCS), built on Emerson OVATION Distributed Control Sys-Vrbina 12, 8270 Krško, Slovenia t e m (DCS) platform and installed by the Westinghouse Electric Companydarko.cicvaric@nek.si at the Krško Nuclear Power Plant as the replacement for the DEH Mod II

turbine control system. Core of the PDEH system consist of three pairs ofredundant controllers (ETS, OA/OPC and ATC/MSR) configured for the

Turbine Generator (TG) set protection, control and monitoring functions.

Existing serial data link between replaced DEH Mod II and Process Information System (PIS) was re-moved and replaced with redundant bi-directional Ethernet TCP/IP data link via two Data Link serversin client-server architecture configuration. All hardwired signals and some of the important calculatedsignals are being transferred from PDEH to PIS. Main purpose of PIS data link is trending utilization atthe existing PIS workstations with pre-configured trend groups and centralized data archiving. Most ofthe PDEH display screens (mimics) were also replicated on the PIS platform, so that TG set monitoringand operation overview can be performed over the PIS network as well as over the Process ComputerNetwork (PCN) with PMSNT-view utility.

The simulator is implemented using a stimulated Windows based Ovation platform and a SGI IRIX basedPlant Model Computer (PMC) using the L-3 MAPPS simulation software platform. Two PDEH stimu-lated systems are installed at the Krško Full Scope Simulator (KFSS), one for foreground and another forbackground simulation. Stimulated PDEH hardware is essentially identical to that installed in the plantwith the exception of hardware redundancy, isolation features and interface with physical plant I/O. TheOvation control logic sheets are executed with virtual controllers hosted on a simulator specific VirtualController Host (VCH) Workstation. The data interface between the simulator Ovation system and thePMC is accomplished through the Ethernet communication using TCP/IP protocol.

Keywords:programmable digital electro hydraulic system, turbine control system, ovation, simulator, pro-cess information system, NPP Krško

1Q SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME.DKWI ffi 9 7Y\ ?

S4-56

Successful Operation of the Only CANDU TypeReactor in Europe

S3O

D

POMPILIU BUDULAN This paper provides highlights of the Romanian Nuclear Program evo-SNNuclearelectrica SA lution since its beginning up to now. The paper presents the evolutionStrada Polona nr.65, Sector 1, a n ^ general description of Romanian Nuclear Power Sector organization,Bucuresti, Romania especially of the Romanian nuclear power company "Societatea Nation-pbudulan@nuclearelectrica.ro ala Nuclearelectrica S.A" short description of the Cernavoda NPP, units

design characteristics, main milestones achievements in Cernavoda NPPconstruction and commissioning, status of the Cernavoda NPP Units,

evolution of the Performance indicators of Cernavoda NPP in commercial operation and main majorOperation problems that Cernavoda NPP faced them.

Keywords: nuclear, Cernavoda, power

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SESSION 4: Operation and Maintenance Experience (OME) 49

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND fi-UIDIL'.̂ . ) H R T 0 0 0 0 4 4 ; i ::T| I

S4-76

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Advanced Approach of Reactor Pressure Vessel Head Inspectionand Repair of CRDM J-Weld

MLADEN PAJNIĆ,HRVOJE FRANJIĆ,GABRIJEL SMOLJKIĆ,KRUNOSLAV MARKULIN,FRAN JARNJAK"INETEC" Institute for NuclearTechnologyDolenica 28,10250 Lučko,Zagreb, Croatiamladen.pajnic@inetec.hr,hrvoje.franjic@inetec.hr,gabrijel.smoljkic@inetec.hr,krunoslav. markulin@inetec.hr,fran jarnjak@inetec.hr

A L E Š V U Č A J N K

MPPKrškoVrbina 12, 8270 Krško,Sloveniaales.vucajnk@nek.si

The reactor pressure vessel head (RPVH) of Pressurized Water Reac-tors (PWR's) is an integral part of the reactor coolant pressure boundary.Its integrity is important to the safe operation of the plant. RPVH haspenetration nozzles for instrumentation systems and control rod drivemechanisms. The discovery of leaks and nozzle cracking at the US NPPand some other PWR plants has made clear the need for more effectiveinspections of RPV heads and associated penetration nozzles. Alloy 600RVHP nozzles & corresponding J-welds cracking and leaking phenomenahave been strictly regulated by NRC Order EA-03-009 since 2003. Someadditional events on this component (Canopy Seal welds, Thermal sleeve,Control Rods Drive Mechanism...) in nuclear industry have raised con-cerns about the structural integrity of RPVH and consequently increasedextent of Non Destructive Examination employing new state-of-the artNDE and repair methods.

This article presents non destructive examination of Reactor PressureVessel Head (RPVH) Penetration by various methods. The scope of thisexamination and repair methods includes Eddy Current examination ofRPVH J-weld surface, ultrasound examination of Penetration Tube frominner side and unique method of surface indications removal.

These article present details of examination techniques with focus oneddy current and ultrasonic examination, as well as details and approach on AST (Automatic SurfaceTreatment) method of the RPVH J-weld surface.AST repair method represents new principal approach with combination of design basis justification andAs-built measurements which provide to perform repair of J-weld indications without any welding.

Keywords: RPVH inspection, CRDM grinding

SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MLi-Xil .. .;'. H R 1 0 0 0 0 4 5i .- .

S4-77

Advanced Approach of Reactor Pressure VesselIn-Service Inspection

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MLADEN PAJNIĆ,KRUNOSLAV MARKULIN,ALOJZIJE MATOKOVIĆ,HRVOJE FRANJIĆ

"INETEC" Institute for NuclearTechnologyDolenica 28, 10250 Zagreb,Croatiamladen.pajnic@inetec.hr,krunoslav.markulin@inetec.hr,alojzije.matokovic@inetec.hr,hrvoje franjic@inetec.hr

The most important task of every utility operating a nuclear power plantis the continuously keeping of the desired safety and reliability level. Thisis achieved by the performance of numerous inspections of the compo-nents, equipment and system of the nuclear power plant in operation andin particular during the scheduled maintenance periods at re-fueling time.Periodic non-destructive in-service inspections provide most relevant cri-teria of the integrity of primary circuit pressure components. The task isto reliably detect defects and realistically size and characterize them.

One of most important and the most extensive examination is a reactorpressure vessel in-service inspection. That inspection demand high stan-dards of technology and quality and continous innovation in the field ofnon-destructive testing (NDT) advanced technology as well as regardingreactor pressure vessel tool and control systems.

This article presents remote underwater contact ultrasonic inspection equipment and developed ad-vanced nondestructive techniques for the examination of the defined sections (reactor welds). Eddy cur-rent method applies for clad surface examinations; visual inspection is used for examination of the vesselinner surface and advanced phased array ultrasonic technique applies for base material examination. Themovement of probes and data positioning are assure by using new RPV tool concept that is fully inte-grated with NDT systems.

The successful performance is attributed thorough pre-outage planning, training and successful perfor-mance demonstration qualification of chosen NDT techniques on the specimens with artificial and/orreal defects. Furthermore, use of advanced approach of inspection through implementation the state ofthe art examination equipment significantly reduced the inspection time, radiation exposure to examina-tion personnel, shortening nuclear power plant outage and cutting the total inspection costs.

Keywords: RPV inspection, phased array, ultrasonic

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SESSION 4: Operation and Maintenance Experience (OME) 51

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AN.., \'JurJiVJ.HIR1.00004.6;

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S4-78

System for Eddy Current Inspectionof WER-440/1000 SG's Tubes

oI

MLADEN PAJNIĆ,KRUNOSLAV MARKULIN,HRVOJE FRANJIĆ,SERGIO GALOŠIĆ

"INETEC" Institute for NuclearTechnology28 Dolenica, 10250 Lučko,Croatiamladen.pajnic@inetec.hr,krunoslav.markulin@inetec.hr,hrvoje.franjic@inetec.hr,Sergio.galosic@inetec.hr

The most important task of every utility operating a nuclear power plantis the continuously keeping of the desired safety and reliability level. Thisis achieved by the performance of numerous inspections of the compo-nents, equipment and system of the nuclear power plant in operation andin particular during the scheduled maintenance periods at re-fueling time.Periodic non-destructive in-service inspections provide most relevant cri-teria of the integrity of primary circuit pressure components. The task isto reliably detect defects and realistically size and characterize them.One of most important and the most extensive examination is a SteamGenerator (SG) in-service inspection. That inspection demand high stan-dards of technology and quality and continual innovation in the field ofnon-destructive testing (NDT) advanced technology as well as regardingSG inspection tools, control systems and techniques.

This article presents overview of the system for SG examination with focus on bobbin and array probeseddy current of the tubes, ultrasonic examination of SG collector welds and service - mechanical plug-ging of the tubes.

Keywords: eddy current inspection, VWER-440, SG tubes

52 SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MI

Auxiliary System Load Schemes in Large Thermal andNuclear Power Plants

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IGOR KUZLE, Uninterrupted auxiliary system power supply in large power plants is a key QDARJAN BOŠNJAK, factor for normal operation, transient states, start-ups and shutdowns andHRVOJE P A N D Ž I Ć particularly during fault conditions. Therefore, there are many challengesUniversity of Zagreb, Faculty in designing the main electrical system as well as the auxiliary systemsof Electrical Engineering and power supply. Depending upon the type of fuel used and the environmen-Computing tal control system required, a thermal power plant may consume as muchUnska 3,10000 Zagreb, Croatia as 10% of its total generation for auxiliary power, while a nuclear powerigor.kuzle@fer.hr, plant may require only 4 - 6 % auxiliaries. In general, the larger the powerdarjan.bosnjak@fer.hr, generating plant, the higher the voltage selected for the AC auxiliary elec-hrvoje.pandzic@fer.hr t d c s y s t e m M o s t s t a t ions in the 75 to 500 MW range utilize 4,2 kV as the

base auxiliary system voltage. Large generating stations 500 - 1000 MWand more use voltage levels of 6,9 kV and more. Some single dedicated loads such as electric driven boilerfeed pumps are supplied ba a 13,8 kV bus. While designing the auxiliary electric system, the followingareas must be considered: motor starting requirements, voltage regulation requirements, short-circuitduty requirements, economic considerations, reliability and alternate sources. Auxiliary power supplycan't be completely generalized and each situation should be studied on its own merits to determine theoptimal solution. Naturally, nuclear power plants have more reliability requirements and safety designcriteria. Main coolant-pump power supply and continuity of service to other vital loads deserve specialattention.

This paper presents an overview of some up-to-date power plant auxiliary load system concepts. Themain types of auxiliary loads are described and the electric diagrams of the modern auxiliary systemsupply concepts are given. Various alternative sources of auxiliary electrical supply are considered, theadvantages and disadvantages of these are compared and proposals are made for high voltage distributionsystems around the thermal and nuclear plant. Arrangements for DC supply systems and uninterruptablepower supply (UPS) systems are also discussed.

Keywords: auxiliary electric system, thermal power plants, nuclear power plants

SESSION 4: Operation and Maintenance Experience (OME) CO

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND' /vIEDii::. HKHJoU

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NPP Krško Approach to Pressure Locking and Thermal Bindingin Motor Operated Valves

TOMISLAV BAJS,MATIJA BALIĆENCONET d.o.o.Miramarska 20,10000 Zagreb,Croatiatomislav.bajs@enconet.hrmatija.balic@enconet.hr

IVICA BASIC,IVAN VRBANIĆ

APoSS d.o.o.Repovec 23B, 49210 Zabok,Croatiabasic.ivica@kr.t-com.hrivan.vrbanic@zg.t-com.hr

BOGOLJUB SEMBER,N E N A D DJETELIĆ

NPP KrškoVrbina 12, 8270 Krško,Sloveniabogoljub.sember@nek.sinenad.djetelic@nek.si

Pressure locking and Thermal Binding are two different but related physi-cal phenomena, which under certain conditions may prevent the openingof some types of Motor Operated Valves.US Nuclear Regulatory Commission (NRC) informed and gave guidancefor preventing pressure locking and Thermal Binding (PL/TB) phenom-ena in GL 89-10 "Safety-Related Motor-Operated Valve Testing And Sur-veillance", and its Supplement 6. Further action has been required by issu-ing GL 95-07 "Pressure Locking And Thermal Binding Of Safety-RelatedPower-Operated Gate Valves" that required evaluation of operational con-figurations of all safety-related power operated gate valves for susceptibil-ity to PL/TB. Corrective actions are required for susceptible valves thatshall assure performance of safety function within plant licensing bases.

NPP Krško (NEK) first addressed this issue through the analysis of theMOV valves that were included in the NEK MOV program. This approachresulted with 31 valves in Krško NPP being found as susceptible to TB, 21of which to both TB and PL.Subsequently, a more detailed analysis was performed, which took intoaccount realistic operational parameters and detailed evaluation of likelyscenarios. This produced a list of 8 valves susceptible to Pressure Locking,and another 8 susceptible to Thermal Binding.Methods used and results produced are the subject of this paper.

Keywords: nuclear power, pressure locking, thermal binding, motor operated valve

"A SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL-CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND Nr.-'J-iL1.".'. H R 1 0 0 0 , 0 4 9i

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Component Cooling Heat Exchanger Heat TransferCapability Operability Monitoring

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M A R I O M I H A L I N A , The ultimate heat sink (UHS) is of highest importance for nuclear power QN E N A D DjETELIĆ plant safe and reliable operation. The most important component in line &NPPKrško from safety-related heat sources to the ultimate heat sink water body isVrbina 12, 8270 Krško, a component cooling heat exchanger (CC Heat Exchanger). The Com-Slovenia ponent Cooling Heat Exchanger has a safety-related function to transfermario.mihalina@nek.si, the heat from the Component Cooling (CC) water system to the Servicenenad.djetelic@nek.si Water (SW) system. SW systems throughout the world have been the root

of many plant problems because the water source, usually river, lake, seaor cooling pond, are conductive to corrosion, erosion, biofouling, debris

intrusion, silt, sediment deposits, etc. At Krško NPP, these problems usually cumulate in the summerperiod from July to August, with higher Sava River (service water system) temperatures.Therefore it was necessary to continuously evaluate the CC Heat Exchanger operation and confirm thatthe system would perform its intended function in accordance with the plants design basis, given as aminimum heat transfer rate in the heat exchanger design specification sheet.The Essential Service Water system at Krško NPP is an open cycle cooling system which transfers heatfrom safety and non-safety-related systems and components to the ultimate heat sink the Sava River. Thesystem is continuously in operation in all modes of plant operation, including plant shutdown and refuel-ing. However, due to the Sava River impurities and our limited abilities of the water treatment, the systemis subject to fouling, sedimentation buildup, corrosion and scale formation, which could negatively im-pact its performance being unable to satisfy its safety related post accident heat removal function. Lowtemperature difference and high fluid flows make it difficult to evaluate the CC Heat Exchanger due to itsspecific design. The important effects noted are measurement uncertainties, nonspecific construction,high heat transfer capacity, and operational specifics (e.g. using CC Heat Exchanger bypass valves for CCtemperature control, variation of plant heat loads, pumps performance, and day-night temperature dif-ference, with lagging effects on heat transfer dynamics).Krško NPP is continuously monitoring the Component Cooling (CC) Heat Exchanger performance usingthe on-line process information system (PIS). By defining the mathematical algorithm, it is possible tocontinuously evaluate the CC Heat Exchanger operability by verifying if the heat transfer rate calculationis in accordance with the heat exchanger design specification sheet requirements. These calculations arelimited to summer periods only when the bypass valves are neither throttled nor open.

Keywords: component cooling, heat exchanger, operability monitoring

SESSION 4: Operation and Maintenance Experience (OME) C tZ

.2 8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND r/XiyS-L-.l H ^ J P P 0 0 5 0 y ;'j).cSU•* S4-96c>

| Requirements and Possibilites for Operational Experience Feedbacko- from the Plant's Manufacturer's Point of View

PETER SCHIM ANN A large amount of nations has realized that nuclear energy can contributeAREVA NP GmbH sustainably to secure their national energy supply. In the last few years,Installed Base Engineering apart from the established nuclear nations, other, often smaller countriesIBE1-G have also decided for themselves to apply the nuclear option to secureKoldestrafie 16,91052 their energy supply. This partly takes place in multi-national cooperationErlangen, Germany between neighboring countries on one side, as well as otherwise betweenpeter.schitnann@areva.com different companies on the manufacturers'/utilities' side.

The endeavor of building absolutely safe reactors and of operating them safelyrequires the necessity on different levels of considering existing and up to date experiences gained in all thenuclear projects' phases. The long time period of many years between the decision on building a nuclear powerplant, the licensing procedure, the detailed planning, the construction phase and the commissioning of theplants, results in the necessity of having to incorporate the constant experience gain on all technical and ad-ministrative levels. This applies to the safety-related boundary conditions in the frame of a new-build projectin the same way as for updating measures performed on existing plants. An often neglected fact, this also ap-plies to the right choice of the guidelines to be applied, to an efficient and competent authority and utility bodyor to the integration of the appropriate technical specialists and experts. Therefore the utilities and their tasksare confronted with different requirements, depending on whether they are located in the country of respon-sible nuclear power plant utilities' head quarters or whether they are simply co-owners of a foreign plant.

AREVA as company covering the complete nuclear cycle including the corresponding plant constructionsupports its partners in all project phases including the development of national institutions and knowl-edge transfer. All of AREVA's existing knowledge - even the recently obtained - is integrated directly inthe corresponding projects.

A special aspect concerning this matter is the resulting operational experience feedback related to eventsin nuclear power plants in operation inland and abroad. Hereby the issue of learning from mistakes madeby others is addressed. Therefore improvements can already be implemented in the planning stage ofnew plants while also defects and failure events in operating plants can be avoided sustainably. Thereforesmaller countries or countries that want to build their first nuclear power plant, participate more notably.AREVA carries the operational experience feedback out for both its own product portfolio, in the frameof know-how and know-why transfers and for stipulations with nuclear power plants organized in theVGB PowerTech (Technical Association of power and heat generators).

The focus of the following discussion lies on the presentation of the volume and the returns of such astipulation in daily business.

Keywords: operational experience, plant, manufacturer

SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEIJIU.Yi i-\Mjv. 'P9, < $0

S4-98

Next Generation of ECT Software for Data Analysis ofSteam Generator Tubes

FRAN JARNJAK,ŠAŠA REŠKOVIĆ,EDO PICEK

"INETEC" Institute for NuclearTechnologyDolenica 28,10250 Zagreb(Lučko), Croatiafran.jarnjak@inetec.hr,sasa.reskovic@inetec.hr,edo.picek@inetec.hr

Improvements to existing EddyOne eddy current analysis software are be-ing presented. Those improvements are geared towards improved inter-action between the software and ECT analyst by having a better and morefeatured user interface, while keeping some industry standard signal dis-play norms intact to keep the familiar factor and ease the transition to thenext generation of EddyOne. Improvements presented in this paper thusease the transition to the new software by reducing training requirementsfor the existing analysts and for new analysts coming to the industry. Fur-ther, by utilizing modern technologies next generation of software is ableto further reduce maintenance and deployment costs of the whole systemfor future to come.

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Keywords: eddy current, NDT, software, analysis

SESSION 4: Operation and Maintenance Experience (OME) 57

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M; r,:< ;lu . VlC }c d • - - -

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Turbine Control System Replacement at NPP NEK;System Specifics, Project Experience and Lessons Learned

D A M I R M A N D I Ć The main intention of this paper is to present feedback from the imple-NPP Krško mentation of the new Turbine Control System (TCS) replacement projectVrbina 12, 8270 Krško, a t Nuclear Power Plant (NPP) NEK - Krško. From the plant construc-Slovenia tion time and the first plant start-up in 1981, the NPP NEK TG (Turbine-damir.mandic@nek.si Generator) set was controlled and monitored by DEH (Digital ElectroM A R K JAMES ZILAVY Hydraulic) Mod II Control System designed in 70s based on P2500 CPU

and number of I/O controllers and modules. The P2500 CPU and asso-es ing ouse ec ric dated controllers were built with discrete TTL components (TTL logic

chips) and the P2500 CPU had 64k of 16 bit words of ferrite core memory.w , , ' For that time, DEH Mod II had sophisticated MCR (Main Control Room)PA-15086 USA HMI (Human Machine Interface) based on digital functional keyboards,zilavymj@westinghouse.com o n e alphanumeric black & white CRT monitor and printer.

After twenty eight years of operation and because of several other reasonsthat are explained in the paper, NEK decided to replace the old DEH Mod

II Control system with the new Emerson Ovation' based DCS (Distributed Control System) on redundantplatform for the control and monitoring of secondary plant systems in the NPP Krško (NEK), and thenew system was named PDEH (Programmable Digital Electro Hydraulic) TCS. In May 2007, NEK signedthe turn-key contract with Westinghouse Electric Company (WEC) for the project of replacement of theTCS, Turbine Emergency Trip System (ETS), Moisture Separator Reheater (MSR) control and some oth-er control and monitoring functions. WEC subcontracted a number of other companies for equipmentdelivery, AE (Architect Engineering Design) activities, specific software development tasks (changes ofKFSS - Krško Full Scope Simulator and PIS - Process Information System interface) and field installationactivities.The subject project enveloped implementation of PDEH system on three application platforms: BG KFSS(Background KFSS), FG KFSS (Foreground KFSS) and PDEH system installed in the plant. The HMI forthe BG KFSS platform constitutes only of soft panels or monitor graphics (all MCB - Main Control Boardand its controls are available as graphic images on workstations), while the HMI for FG KFSS includes fullscope replica of NEK MCR and MCB.The new PDEH system was installed on two KFSS platforms (BG and FG) in October-November, 2008;pre-outage or on-line field installation work was performed in the January-March 2009 timeframe; whilethe old DEH Mod II was decommissioned and the new plant PDEH system was installed during the out-age in April, 2009 and tested with the plant on line in May, 2009.

SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £' i

PDEH system improvements and specifics compared to the old DEH system and compared to other simi- 2lar references will be presented and the most interesting project experience and lessons learned will also "Jj,be discussed in the paper. g

oKeywords: NEK, Turbine Control System Replacement, DEH Mod II TCS, Ovation g.

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Qualification Practices in Nuclear Industry: Steam GeneratorEddy Current Probe Qualification

MATIJA VAVROUŠ, Through history of nuclear power plant operation, a large number of nu-RENATO G R A C I N clear power plant forced outages related to tube failures occurred. It re-"INETEC - Institute for suited with large amount of repair and outage costs, what initiated imple-Nuclear Technology" mentation of regulated practice of periodical tube examination and tubeDolenica 28,10250 Zagreb, condition monitoring. Purpose of examinations is to detect existing orCroatia potential tube degradations that could affect tube integrity and thereforematija.vavrous@inetec.hr, result in forced outages and unwanted costs related to emergency repairrenato.gracin@inetec.hr activities and loss of ability for electrical power production.

With increased examination activities, additional information aboutsteam generator tube condition became available and additional methods for ensuring tube integritybecame available. As the number of examination solutions increased, need for validation and assessmentof examination methods occurred. For that purpose, a large number of standards and guidelines with itsrequirements were implemented in nuclear industry regulatory requirements to ensure that adequatelyvalidated examinations are applied. With this purpose, qualification requirements for inspection activi-ties were implemented with other requirements.

With progress of technology, progress was also achieved in examination methods and more advancedexamination methods and advanced inspection systems were developed. This advancement is accompa-nied by advancement in regulatory requirements regarding inspection and monitoring of tube integrityand condition.

Ultimate goal of implementation of qualification processes and its requirements in all aspects of nuclearindustry is to achieve minimal rate of forced outages, which would ensure maximum electrical powerproduction capabilities and maximum optimization of operational costs while maintaining safe operationin accordance with environmental policies.This article will focus on qualification of steam generator eddy current bobbin probe.

Keywords: qualification practice, SG eddy current probe

SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME i-HUM ! ;.• r ' i V

S4-113

Automation of Shift Work in Operations ©

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MLADEN DUDAŠ NPP Krško has started with Operations shift work automation in 2009. The QNPP Krško main goal is to establish complete equipment and systems status control ftVrbina 12, 8270 Krško, by electronic mean in next two years (until outage 2012). Other benefitsSlovenia that can be attained with such automation are: operations performancemladen.dudas@nek.si improvement (immediate response), better interaction (communication)

among plant personnel, reduction of possible human errors, outage shiftwork optimization, reduced repetitive work, availability of on-line information related to plant operation.To achieve the plant status control by electronic mean, various shift work processes in operations mustbe automated and integrated such as:

- Operator rounds

- Narrative Logs

- Tagging process

- Equipment deficiencies tracking

- Plant Technical Specifications monitoring system

- Temporary modifications

- Personnel Qualifications and Scheduling (working hours control)

- Personnel authorization

- Notification (Obligatory readings)

- Key control

Before implementation of shift work processes automation there are some prerequisites that must be ful-filled. Technically very important is to have precisely defined processes, good equipment data base withdefined components and subcomponents and consistently labeled equipment. Domestic law require-ments should be checked for conformity related to documents authorization. All relevant bodies whichparticipate in decision making within the plant and outside organizations (regulatory authority - SNSA,Energy and Mining Inspectorate) should be acquainted with the plant intention to replace old way of ad-ministering to new way. This paper gives details on the software features, implementation, and lists anddiscusses difficulties that can arise during such change.

Keywords: operations, shift work, automation

SESSION 4: Operation and Maintenance Experience (OME) £. 1

:a 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL Af::."s *]?•)U 4.f?iP.P.Q;055v

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High Partial Discharge Levels in Nuclear PowerPlant Turbo-Generator

ZORAN BERTALANIĆ,MILUTIN PAVLICAEnergy Institute Inc.Ulica grada Vukovara 37,10000 Zagrebzoran.bertalanic@ie-zagreb.hr,milutin.pavlica@ie-zagreb.hr

ZLATKO MALJKOVIĆ

University of Zagreb, Facultyof Electrical Engineering andComputing University of ZagrebUnska 3,10000, Zagrebzlatko.maljkovic@fer.hr

On-line measurement of partial discharge (PD) is commonly known methodfor assessment of armature winding condition. Since it can be carried outwhile the machine is in operation, it is considered by many to be the mostrealistic one. PD pulses are forwarded to measuring instrument using capaci-tive couplers connected to generator's armature winding. Magnitude, polar-ity and phase angle relative to phase-to-ground voltage are measured for ev-ery pulse and further analysed by statistical approach. A number of problemswith armature winding can be registered and diagnosed by PD method.The paper presents results of PD measurements and their analysis in caseof large synchronous turbo-generator, 812 MVA, 21 kV, cos<p=0.85, 50 Hz,1500 min1, manufactured in 1979 and installed in Nuclear Power PlantKrsko, Slovenia. The generator is cooled by hydrogen, with armature wind-ing directly cooled by water. The turbine-generator set's rated power hasbeen increased from original 660 MW twice: in 2000 up to 690 MW and in

2004 up to 730 MW. There have been no modifications on generator regarding the power increase.The generator has a history of high PD activity. On-line PD monitoring system was installed in 2004. Paperpresents results of PD measurements in NPP Krsko carried out in 2009. Registered PDs were almost 8 timeshigher than 95% of typical PDs measured for similar turbo-generators, their magnitude for constant activepower varies with ratio 1:100, their phase distribution lies around 0° and 180°, (indicating that their cause isoutside of slots and of mechanical origin), their main source migrates from phase to phase, they are cross-coupling to other phases (indicating that their origin lies in part of generator where all three phases are close)and their phase occurrence varies with constant active power and varying reactive power.

All other types of performed off-line measurements and tests have not shown any signs of severe deteriora-tion or any other problem in generator stator winding insulation.So far, none of the theories about the origin of the PDs have been confirmed and no source of PDs has beenfound. Stator winding and core will soon be replaced and it will be interesting to see whether any additionalrelevant information will be acquired during the replacement process.

Keywords: turbo-generator, insulation testing, partial discharges

CS% SESSION 4: Operation and Maintenance Experience (OME)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £l

Session 5Safety Culture (SC) to

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Nuclear Security and Nuclear Security Culture 64S5-36 R.BIŠĆAN

Supplier Assessment and Auditing Process 65S5-38 B. MANCHEV, B. NENKOVA, E. TOMOV

Quality and Safety Assurance - Priority Task at Nuclear PowerProjects Implementation 66

S5-45 B. BožiN, D. KAVŠEK

Nuclear Oversight Function at Krško NPP 67S5-50 A. ROŽMAN, A. ANDROJNA

The Role of Occupational Health and Safety in Complex OutageServices to NPPs 68

S5-70 A. KUŠAR, D. KAVŠEK

Krško Nuclear Power Plant's Environmental ManagementSystem in Compliance with ISO 14001:2004 69

SESSION S: Safety Culture (SC) /: '*

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Nuclear Security and Nuclear Security Culture

A N K I C A CIŽMEK Threats to nuclear security involve criminals or terrorists acquiring andState Office for Nuclear Safety using for malicious purposes: (a) nuclear weapons, (b) nuclear material toUlica grada Vukovara 284 build improvised nuclear explosive devices, and/or (c) radioactive mate-10000 Zagreb, Croatia rial to cause harm to individuals or the environment, including the con-ankica.cizmek@dzns.hr struction of radiological dispersal devices (RDDs). Such threats could also

include (d) the dispersal of radioactivity through the sabotage of facilitiesin which nuclear material and radioactive material can be found or of such material in transport.

A nuclear security framework includes a range of elements including: legislation and regulation; assess-ment of the threat to nuclear and other radioactive material and associated facilities; administrative sys-tems; various technical hardware systems; and, mitigation activities. No single organization or subsectionof an organization can address these elements in isolation. A healthy nuclear security culture is depen-dent on proper planning, operation and maintenance.

Keywords: nuclear security, nuclear safety, nuclear safety and security culture

CA SESSION 5: Safety Culture (SC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME lUU.Vl Li. HR'1 0 0 0 0 5 7 '

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Supplier Assessment and Auditing Process

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ROMEO BIŠĆAN Supplier assessment shall be carried by Audit: Qo

NPPKrsko , Before awarding a contract or placing a purchase order to assess Supplier £Vrbina 12, 8270 Krško, capability and the adequacy of its Management System/QA Program;romeo.biscan@guest.nek.si * A f t e r a w a r d i n S a contract to assess whether the Supplier is appropri-

ately performing the function as defined in the Management System/QA Program, applicable Codes and Standards, regulatory and othercontract requirements;

• When significant changes are made in the Supplier s Management System/QA Program;• When it is suspected that the quality of a product or service is in jeopardy caused by nonconformance

to regulatory requirements or Management System/QA Program.

Supplier Audit shall be scheduled and the frequency of assessment is determined by importance of prod-uct/service and the performance of Supplier, but Supplier Audit shall be performed at least once per threeyears for continuous supply.Methodology of assessment is based on evaluation of Management System/QA Program compliance toCodes/Standards, regulatory and contract requirements; documentation and records review; observationof how process and activities are being performed; management and personnel interviews; adequacy andefficiency of Corrective Action Program etc.

10CFR50 Appendix B assessment criteria for different Suppliers are applied regarding to product or ser-vice to be supplied: Design Services; Engineering Services; Laboratories Services; Construction/Installa-tion Services; Equipment Supplier; Material Supplier; Field Services.

Keywords: assessment, audit, supplier, management system, QA program, quality

SESSION 5: Safety Culture (SC) & Ej

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Power Projects Implementation

g-o Quality and Safety Assurance - Priority Task at NuclearQoo

BOYKA NENKOVA Quality and safety assurance at implementation of nuclear power engineer-GCR Ltd. ing projects is important and difficult task for realization. Many problems10 Vihren Str., 1618 Sofia, a f i s e during this process, when many companies from different countriesBulgaria participate, with various kinds of activities and services provided.boyka.nenkova@riskeng.bg x/he scope of activities necessary for quality and safety assurance is there-B O G O M I L M A N C H E V ,

f o r e quite expanded and diverse.EMIL TOMOV In order to increase the safety and reliability of Kozloduy NPP Pic (KNPP)Risk Engineering Ltd Units 5 & 6, as well as to bring the units in conformity with the newest10 Vihren Str., 1618 Sofia, international requirements for quality and safety in the field of nuclearBulgaria energy, a program for their modernization on the basis of different techni-bogomil.manchev@riskeng.bg, cal studies and assessments was implemented. The Units 5 & 6 Modern-tomov@riskeng.bg ization Program of Kozloduy Nuclear Power Plant was composed of 212

modifications aimed to improve the safety, operability, and reliability ofthe Units. The Program was realized by stages during yearly planned out-

ages since year 2002 to 2007, without additional outages.

A major Program objective was to extend the units life time in at least 15 Years, under a continuous, safe,and reliable operation.

The Modernization Program of Units 5 and 6 of the Bulgarian Nuclear Power Plant in Kozloduy was thefirst and for the time being the only one in the world, program in the field of nuclear power engineering,by which the full scope of recommendations for improvement of the Kozloduy NPP units was applied.

The main goal of the National Electric Company, which is the Employer for the construction of newnuclear facility in Bulgaria, is after completion of all activities regarding construction of Belene NPP theplant to meet or exceed the requirements of the respective national and international quality and safetycodes and standards, as well as the IAEA guidelines, as they are established.

The objective of this report is to describe different aspects of the quality assurance according to the re-quirements of quality and safety standards at implementation of complex energy projects. Experience isshared on the basis of implementation of the Units 5&6 Modernization Program of Kozloduy NPP andthe project "Construction of Belene NPP" Examples are given related to the definite quality improvementgoals achievement in case of participation of big multinational and international companies.

Keywords: KNPP, Belene, quality and safety assurance

SESSION 5: Safety Culture (SC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM E! : H R t 0 0 0 Q 5 9

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Nuclear Oversight Function at Krško NPP

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BOJAN BOŽIN, The nuclear oversight function is used at the Krško NPP constructive- QDARKO KAVŠEK ly to strengthen safety and improve performance. Nuclear safety is kept &NPP Krško under constant examination through a variety of monitoring techniquesVrbina 12, 8270 Krško, ar>d activities, some of which provide an independent review. The nuclearSlovenija oversight function at the Krško NPP is accomplished by Quality and Nu-bojan.bozin@nek.si, clear Oversight Division (SKV). SKV has completed its mission throughdarko.kavsek@nek.si a combination of compliance, performance and effectiveness-based as-

sessments. The performance-based assessment is an assessment usingvarious techniques (observations, interviews, walk-downs, document reviews) to assure compliance withstandards and regulations, obtain insight into performance, performance trends and also to identify op-portunities to improve effectiveness of implementation.Generally, the performance-based approach to oversight function is based on some essential elements.The most important one which is developed and implemented is an oversight program (procedure). Theprogram focuses on techniques, activities and objectives commensurate with their significance to plantoperational safety. These techniques and activities are: self-assessments, assessments, audits, perfor-mance indicators, monitoring of corrective action program (CAP), industry independent reviews (suchas IAEA's OSART and WANO Peer Review), industry benchmarking etc.

Graded approach is an inherent product of a performance based program and ranking process. It is im-portant not only to focus on the highest ranked performance based attributes but to lead to effective uti-lization of an oversight program. The attributes selected for oversight need to be based on plant specificexperience, current industry operating experience, supplier s performance and quality issues.

Collaboration within the industry and effective utility oversight of processes and design activities are es-sential for achieving good plant performance. So the oversight program must integrate relevant industryexperience (events, good practice etc.) in its assessment. That becomes most important in small utilities(with one nuclear unit only) such as the Krško NPP. Involvement in international organizations is there-fore a must and not an option for such organization. The Krško NPP is today widely involved in variousinternational organizations. Both sides are deriving substantial benefits from such cooperation.

Keywords: nuclear oversight, performance-based assessment, international organizations

SESSION S: Safety Culture (SC)

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEiVlto2U

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3oCN

I

S5-50

The Role of Occupational Health and Safety inComplex Outage Services to NPPs

AMBROZ ROŽMANQ TECHNA d.o.o.,CKŽ 135e, 8270 Krško, Sloveniaambroz.rozman@qtechna.si

ANDREJ A N D R O J N A

NUMIP d.o.o.,CKZ 135e, 8270 Krsko, Sloveniasiandrej.androjna@numip.si

Meeting outage schedules in NPPs which are increasingly demanding,apart from all other aspects, introduces a new perspective on occupation-al health and safety (OHS).

Not only is the OHS a constituent part of a plants overall outage manage-ment, it above all dictates paramount objectives to outage service provid-

The paper reviews the impacts of reductions of outage durations on OHSa n d presents related experience of the leading Slovenian outage servicesprovider, NUMIP d.o.o. over the last ten years. The company is now get-ting prepared for its 12th outage at Krško NPP in 2010, and has not have

recorded a major injury so far, even though these projects engaged over 450 people at a time on-site.To achieve such results, a lot of emphasis is being put onto OHS management prior to and during out-ages. A certified OHSAS 18001 system has been established and implemented to further support prepa-ration and execution of NUMIP's outage activities at Krško NPP, and also for other projects. An effectivecontinuous improvement system is built into the project, providing for implementation of lessons learnedfrom domestic and foreign plants.

To illustrate the topic in more detail, a case on a Seismic protection of polar crane project is presented. Ittook plače in the 2009 Outage and has certainly been one of the most demanding projects from the OHSpoint of view for NUMIP so far.

The paper aims at contributing to a better understanding of the role of effective management of OHS onthe side of a service provider, and, consequently, in the overall outage success of a plant.

Keywords: OHSAS 18001, NPP outage

C.Q SESSION 5: Safety Culture (SC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEttH-'.V: 1 .'... '7° ' ;Q9^P§ ' ' :•

S5-70

Krško Nuclear Power Plant's Environmental ManagementSystem in Compliance with ISO 14001:2004

cr33

A N A KUŠAR, Krško Nuclear Power Plant (NPP) pays special attention to environmental QDARKO KAVŠEK protection and practices environmental safety in all plant processes and g.NPP Krško management.

Vrbina 12, 8270 Krško, In 2008, Krško NPP introduced the Environmental Management SystemSlovenija in compliance with ISO 14001:2004 standard.ana.kusar@nek.si, T h e p l a n t m a n a g e m e n t announced the Environmental policy which is adarko.kavsek@nek.si p a r t Qf t n e b u s j n e s s strategy of Krško NPP which is an eco-friendly com-

pany. The Policy is a commitment of the plant management and all staff toact in compliance with requirements of ISO 14001:2004.The standard served as a basis for developing some new documentation such as Environmental Manage-ment System Quality Manual, Environmental planning procedures identifying legal and other require-ments, Register of environmental aspects, Register of legal and other requirements etc.When establishing the Register of environmental aspects, all possible environmental impacts of the plantwere carefully reviewed and estimated.

Following the introduction and certification audit in October and December 2008 of Bureau Veritas Cer-tification, Krško NPP was awarded certificate ISO 14001:2004 attesting conformity of its EnvironmentalManagement System with this standard.

The Environmental Certificate means that Krško NPP will promote a positive environmental culture andmaintain a safe, healthy and environmentally-sound workplace for all its employees, contractors and visi-tors.

Keywords: environmental management system, environmental policy

SESSION 5: Safety Culture (SC)

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDSaoU

.aaoCN

Session 6Nuclear Safety Analyses (NSA)

g S6-24 T. MAUNA

^ Sitting Safety Aspects of Second Romanian NPP 72S6-29 K. FILIPOV, S. PHILIPOV

Code Development for Internal Flooding in NPP and Benchmark Analyses 73S6-37 A. DEL NEVO, M. ADORNI, F. D'AURIA, O. I. MELIKHOV, I. V. ELKIN,

V. I. SCHEKOLDIN, M. O. ZAKUTAEV, S. I. ZAITSEV, M. BENČIK

Enlargement of the Assessment Database for Advanced ComputerCodes in Relation to the WER Technology: Benchmark onLB-LOCA Transient in PSB-VVER Facility 74

S6-48 C. ALLISON, L. SIEFKEN, J. HOHORST, J. BIRCHLEY

Recent Improvements in RELAP/SCDAPSIM/MOD3.4 Resultingfrom QUENCH and PARAMETER Bundle Heating and QuenchingExperiments 75

S6-51 S. ŠADEK, D. GRGIĆ, N. DEBRECIN

Corium Behaviour and the Lower Head Thermal Responseafter a Core Meltdown 76

S6-58 I. VRBANIĆ, I. BAŠIĆ, I. VUKOVIĆ

Krško NPP PSA Update with SG BD System Modifications 77S6-59 I. VRBANIĆ, I. BAŠIĆ, A. ANTOLOVIČ

Methodology for Ranking of the NPP Krsko PSR Issues 78S6-63 C. MATTEOLI, G. NACCI, M. CHERUBINI, A. DEL NEVO, F. DAURIA

Study of CCFL Phenomenon Based on University ofHannover Experiments 79

S6-67 M. CHERUBINI, F. MORETTI, F. D'AURIA, S. H. AHN, Y. J. CHO, T. HOEHNE

Independent Assessment of MARS 3D Features: Use ofExperimental Data and CFD Support 80

7/ SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

too

S6-68 D. GRGIC, V. BENČIK, S. ŠADEK, N. ČAVLINA 2RELAP5 Modelling of PWR Reactor RTD Bypass 81 g

S6-82 Z. ŠIMIĆ, V. MlKULIČlĆ Oc

On the Screening of Other External Events: Explosions and g"Hazardous Release Evaluation 82 2.

S6-116 D. KONJAREK, T. BAJS, J. VUKOVIĆ Qo

Intermediate Leg SBLOCA - Long Lasting Pressure Transient 83 §S6-120 T. BlLIĆ ZABRIC

Safety Requirements for New Nuclear Facilities 84

SESSION 6: Nuclear Safety Analyses (NSA) "7 I

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL ANDr^R1000062. ,.

2u

l l

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S6-24

Sitting Safety Aspects of Second Romanian NPP

TRAIAN MAUNA

Romanian Nuclear EnergyAssociation-AREN65 Polona, CP. (PO Box)22-102, 010494 BucharestRomaniatraianmauna@rdslink.ro

The first Romanian NPP CANDU 6 type reactor gone to erection in 1980on Cernavoda site planned to have 5 units like the Wolsong applied designproject for nuclear island. For the BOP parts the ASALDO-GE projectwas applied with the careful about the interface connection NSP require-ments. The new NPP sitting studies began from 1982 in a serious manneras first part on Nuclear Power Plant Romanian Program adopted by politi-cal and governmental authorities at the time. For develop the all packageof the studies in concordance with the first IAEA Safety Standards recom-

mendations. Till the 1982 the first mission of design and research multi-branch of specialists team wasto adapt the NPP Cernavoda project having a open water cooling circuit to the new parameters of closewater cooling circuit. But the team was looking at the other type of NPP for sitting. Also in the same timewas studied the possibility of NSP foundation on hard less or soft soil foundation strata in connectionwith safety aspects. The close circuit of cooling water means others parameters of systems and need verylarge cooling towers. Also must be reconsidering the safety systems design and performance as new solu-tion.

In the south of Transylvania historical region in Romania the Olt River run from west to east having me-dium multiannual flow around 70 m3/s. The Olt River has a chain of small hydropower in operation andother planned. From geological and geophysical points of view two main faults, along the Olt river valley,one of this having seismically small activities was detected. Site region geotechnical studies show smallquantity underground natural gas, salt and peat. The initial nuclear program has imposed 4 NPP unitssite near Olt River. Taking into account the orogenesis, water cooling needs and other local feature can'tbe built more than two NPP units on a site. This paper tries to reconsider the old analysis from the lastIAEA Safety Standards point of view taking into account the new NPP generation, focusing on geological,geotechnical and geophysical feature having some references to other safety requirements in order to as-sure the 106 risk events. Also the national electrical network impact will tough.

Keywords: NPP sitting, safety, Romania, CANDU

72 SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ;•:! $ ^ - PQPPQ3 V- ••,

S6-29

Code Development for Internal Flooding in NPP andBenchmark Analyses

KALIN FILIPOV

Technical University - Sofia8 Kliment Ohridski, blvd, Sofia1000, BulgariaDepartment of Thermal andNuclear Power Engineeringfilipov@tu-sofia.bg

SVETLIN PHILIPOV,

Risk Engineering, Ltd

10 Vihren Str, Pavlovo, Sofia1618, BulgariaSvetlin.Philipov@riskeng.bg

The main point of the work is the specific software creation for analyzingthe internal flooding dynamics in NPP (nuclear power plant). Applicabil-ity target is the investigation of the fluids time dependant distribution inthe hermetic compartment system of the NPP. The software product hasthe ability to simulate different flooding initiators and the consequencesof a given safety system operation as spray system, fire extinguishing sys-tem, drainage system and so on. The software includes not only waterdistribution but air-steam flows also. The processes like condensation andevaporation are modelled too. A benchmark analysis is done with com-parison to integral code MELCOR.

Keywords: NPP, internal flooding, numerical calculation, integral code,MELCOR

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SESSIONS: Nuclear Safety Analyses (NSA) 7'»

.2 8T H INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MliOIUA£U

1o

oCN

S6-37

Enlargement of the Assessment Database for AdvancedComputer Codes in Relation to the VVER Technology:Benchmark on LB-LOCA Transient in PSB-VVER Facility

ALESSANDRO DEL NEVO,MARTINA ADORNI,FRANCESCO D'AURIA

University of PisaLargo Lazzarino, 2 56126, Pisa,Italya.delnevo@ing.unipi.it,m.adorni@ing.unipi.it,dauria@ingunipi.it

O L E G I. MELIKHOV,ILYA V. ELKIN

Electrogorsk Researchand Engineering Centre,Electrogorsk, Russiaoleg.melikhov@erec.ru,elkin@erec.ru

VLADIMIR I. SCHEKOLDIN,M A X I M O. ZAKUTAEV,SERGEY I. Z A I T S E V

FSUE EDO "GIDROPRESS",Podolsk, Russiazakutaev@grpress.podolsk.ru

M A R E K BENČIKNuclear Research InstituteRež plc, Czech Republicben@ujv.cz

The OECD/NEA PSB-VVER project provided unique and useful experi-mental data from the large-scale PSB-VVER test facility for code valida-tion. This facility represents the scaled down layout of the Russian de-signed PWR reactors, namely VVER-1000. Five experiments were execut-ed in the project, dealing mainly with the loss of coolant scenarios (small,intermediate, large break loss of coolant accident); a primary to secondaryleak and a parametric study (natural circulation test) aimed at the char-acterization of the VVER system at reduced mass inventory conditions.The comparative analysis described in the paper deals with the analyticalexercise on the large break loss of coolant accident experiment (Test 5).Four participants from three different institutions were involved in thebenchmark and applied their own analytical models, set up for four differ-ent thermal-hydraulic system codes. The benchmark demonstrated thatalmost all performed post-tests appeared qualified against fixed criteria.Few mismatches between the results and acceptability thresholds are dis-cussed and understood. The analysis involves the relevant features of theinput models developed, the steady state conditions and the results of thesimulations. The results submitted by the participants are discussed in thepaper considering the resulting sequence of main events, the qualitativecomparison of selected time trends, the analysis of the relevant thermal-hydraulic aspects and, finally, by the application of the Fast Fourier Trans-form based method.

Keywords: LB-LOCA, PSB-WER

74 SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEIDO/: i.\ \ HR1 000 ,06 .5 .

S6-48

Recent Improvements in RELAP/SCDAPSIM/MOD3.4Resulting from QUENCH and PARAMETER Bundle Heatingand Quenching Experiments

CHRIS ALLISON,

LARRY SIEFKEN,

JUDITH HOHORST,

J. BIRCHLEY

Innovative Systems Software1242 South Woodruff AvenueIdaho Falls, Idaho 83404 USAiss@srv.net, siefken@srv.net,jkh@srv.net

The RELAP/SCDAPSIM code, designed to predict the behaviour of reac-tor systems during normal and accident conditions, is being developed aspart of an international nuclear technology development program calledSDTP. Three basic versions of RELAP/SCDAPSIM are currently sup-ported. MOD3.2 is the oldest production version and includes publiclyavailable RELAP and SCDAP models released by the US Nuclear Regula-tory Commission. This version includes special modeling options neces-sary to represent the electrically heated fuel rod simulators used in theQUENCH facilities. MOD3.4 is the current production version and in-cludes SDTP-developed model improvements including new models and

options designed to support the ongoing QUENCH and PARAMETER experimental programs. MOD4.0is the latest experimental version and includes expanded models and user options such as an integrateduncertainty analysis package.

This paper describes the modelling improvements in MOD3.4 that were specifically added to supportthe ongoing QUENCH and PARAMETER research program. These modelling improvements includethe addition of tantalum and other PARAMETER fuel rod simulator materials and new user options tobetter represent the end fittings and shrouds used in the QUENCH and PARAMETER tests. The paperalso includes representative results from the developmental assessment of the new models using theQUENCH-06 and PARAMETER SF3 experiments.

Keywords: RELAP/SCDAPSIM, RELAP, SCDAP, Quench

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SESSION 6: Nuclear Safety Analyses (NSA) n r

.2 81H INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND .Mti;.: J ' , N R ; 1 0 t 0 P ^ 0 6 6 G R . r } ca —

IS6-51

Corium Behaviour and the Lower Head Thermal Responseafter a Core Meltdown

SlNlŠA SADEK, During a severe accident in a PWR plant, core degradation and meltingDAVOR G R G I Ć , could result in slumping of the molten material to the lower head. TheN E N A D DEBRECIN relocated material will be composed of ceramic (UO2, ZrO2) and metallicUniversity of Zagreb, Faculty (Zr, Fe, Ni) materials whose chemical composition depends on the reac-of Electrical Engineering and tor design, the accident scenario, the core heat-up rate and availabilityComputing, University of of coolant during core degradation processes, thus, on thermal-hydraulicZagreb , behaviour of the reactor coolant system (RCS). If the temperature of thatUnska 3,10000 Zagreb, Croatia mixture is higher than its liquidus temperature (2800-2900 K), the mix-sinisa.sadek@fer.hr, t u r e w[\\ be in the liquid state. The mixture of molten core materials isdavor.grgic@fer.hr, k n o w n a s c o r i u m

nenad.debrecin@fer.hrProduction of decay heat will cause intense natural circulation. Althoughceramic and metallic melts are immiscible, turbulent nature of the flow

will prevent stratification, which might occur due to density difference, and result in negligible spatialtemperature variations. The reactor pressure vessel (RPV) lower head wall in contact with the melt willbe heated up depending on the energy balance between the heat flux from the molten pool and the heatlosses on the outside RPV wall surface. Cooling of the melt results in formation of a crust surroundingcorium which acts as a heat insulator. Therefore, the wall temperature increase will be slowed down bythe presence of the crust. Nevertheless, in the case of a large molten pool present in the lower head, thereis a high probability of the wall melt-through or rupture.In the presented analysis, corium mass and composition corresponded to a prototypic PWR core. ANSYScode was used for the study of corium natural circulation (FLOTRAN) and for the analysis of the RPVwall thermal behaviour.Keywords: severe accident, RPV lower head, corium natural circulation, RPV wall thermal behaviour

SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND

S6-58

Krško NPP PSA Update with SG BD System Modificationsoa"

Evaluations done for the purposes of definition of environmental qualifi-cation zones at Krško NPP have shown that, due to potential pipe ruptureevent in the Steam Generator Blowdown Processing (BD) System, a sig-nificant area in the Intermediate Building could become a "harsh" zone.As a consequence, a number of important components, including theSafety Class DC Batteries, Battery Chargers and Motor Driven AuxiliaryFeedwater Pumps could, potentially, be lost following the break in the SGBD line. The same hazard would also affect the Remote Shutdown Panels(Evacuation Panels), located in the affected area, which could result ininteractions that would possibly affect safety mitigation systems.The SG BD high energy line break (HELB) would, therefore, represent aninitiator with possible significant degradation in plant mitigation capabil-ity. Recognizing this, Krško NPP decided to implement a design modifica-tion and install the equipment that would detect the SG BD line break and

isolate the ruptured pipe in a short time. Additionally, a shielding in the form of steel plates for the CableTrays in the plant room / area IB021 will be installed. This is necessary in order to protect the control andpower cables for the Remote Shutdown Panels from the dynamic effects produced by a HELB event, suchas steam jet impingement, should the postulated break occur in the IB021 area.The Krško NPP PSA model was updated with regard to these plant design modifications and the updatedmodel used to estimate the residual risk from the SG BD HELB events. This included the characterizationof hazard in the form of hazard damage states, plant response analysis to determine the impact of hazardon the plant equipment in the affected rooms, considering also the containment systems, and Level 1 andLevel 2 PSA modelling and risk quantification.

The paper presents the analysis and the results.

Keywords: Krško NPP, PSA, HELB, SG blowdown processing

IVAN VRBANIĆ,IVICA BAŠIĆAPoSS d.o.o.Repovec 23B, 49210 Zabok,Croatiaivan.vrbanic@zg.t-com.hr,basic.ivica@kr.t-com.hr

I G O R V U K O V I Ć

University of Zagreb, Facultyof Electrical Engineering andComputingUnska 3,10000 Zagreb, Croatiaigor.vukovic@fer.hr

no

SESSION 6: Nuclear Safety Analyses (NSA) 77

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND l-Mli.

e —u

•i

S6-59

Methodology for Ranking of the NPP Krsko PSR Issues

oI

IVICA BASIC,IVAN VRBANIĆ

APoSS d.o.o.Repovec 23B, 49210 Zabok,Croatiaivan.vrbanic@zg.t-com.hr,basic.ivica@kr.t-com.hr

ALEKSANDRA ANTOLOVIČ

NPPKrškoVrbina 12, 8270 Krsko,Sloveniaaleksandra.antolovic@nek.si

A Periodic Safety Review (PSR) of a nuclear power plant, typically, re-sults with a number of identified issues of different types. According tothe current IAEA's referential PSR guiding document, the overall reviewis divided into fifteen review areas, termed "safety factors", which rangefrom "plant design" to "human factors" to "safety culture", for example.The method for ranking of identified safety issues must characterize thesafety importance of the issues coming from different review areas or fac-tors on the same scale and consistent basis. For the Krsko NPP s (NEK)second PSR, the method for issue ranking was established which primar-ily evaluates the safety significance of any PSR issue by considering itsimpact on the defense in depth. This impact can be evaluated qualitativelyor quantitatively. The paper presents the methodology and illustrates itsapplication on a selected simple example.

Keywords: periodic safety review, safety issue, ranking, prioritization

78 SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEi-^)*'. n . . 'H^1AQ0Q

S6-63

Study of CCFL Phenomenon Based on University ofHannover Experiments

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There are several structures internal to reactor pressure vessel (RPV),where gravity drainage of liquid can be obstructed by upward flowingvapor. These include the upper core tie plate (UTP), where the countercurrent flow limiting (CCFL) mechanisms may occur during refilling andreflooding phases. Many CCFL data have been carried out with air andwater as well as with steam and water, e.g. UPTF, MHYRESA and Han-nover separate test facilities. In case of steam/water, the CCFL involvesnot only the mechanical interactions but also the thermal exchanges, dueto steam condensation on subcooled emergency core cooling (ECC) water,which might lead to water break-through. The experiments carried out atUniversity of Hannover (i.e. the tests with a 16x16 rod bundle) constitutea suitable database to validate RELAP5 code and to support its applicationin accident analysis (e.g. Atucha-2). These data have been used to studythe CCFL phenomenon. The different options of RELAP5 s CCFL model

are tested to assess the code performance, following the set up of the input deck through the optimiza-tion of the energy loss coefficients (Reynolds independent and dependent as well). Sensitivities are alsoperformed to address the effect of the time step and of the nodalization on the results. The activity isconcluded by investigating the phenomenon in Atucha2 reactor channel geometry.

Keywords: CCFL, MYHRESA, University of Hannover experiment

CAMILLA MATTEOLI,GIULIA NACCI,MARCO CHERUBINI,ALESSANDRO DEL NEVO,FRANCESCO D'AURIA

University of Pisa

Largo Lazzarino, 2 56126, Pisa,Italymatteolicamilla@gmail.com,giulia.nacci@hotmail.it,m.cherubini@ing.unipi.it,a.delnevo@ing.unipi.it,dauria@ing.unipi.it

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SESSION 6: Nuclear Safety Analyses (NSA) • 7 Q

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MP.DIUM KL^R'll.OP

U

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VD

S6-67

Independent Assessment of MARS 3D Features: Use ofExperimental Data and CFD Support

MARCO CHERUBINI,FABIO MORETTI,FRANCESCO D'AURIA

GRNSPG/DIMNP University ofPisa, ItalyLargo Lazzarino, 2 56126, Pisa,Italym.cherubini@ing.unipi.it, f.moretti@ing.unipi.it,f.dauria@ing.unipi.it

S E U N G H O O N A H N ,

YONG-JlN CHO

Korea Institute of NuclearSafety, Daejeon, Koreakl75ash@kins.re.kr,yjincho@kins.re.kr

T H O M A S H O E H N EFZD, Rossendorf, DresdenGermanyt.hoehne@fzd.de

Recent developments of special models and correlations extended the sys-tem TH codes capabilities to simulate 3D phenomena. A code assessmentprocess is always needed whenever the new code features are intended fornuclear reactor design and/or licensing applications. The Korean Ther-mal-Hydraulic code MARS (developed by Korea Atomic Energy ResearchInstitute) experiences such an improvement, extending the ID flow fieldformulation.

In this respect the present paper describes the activity conducted to assessthe 3D features of the MARS code by independent users. The adoptedexperimental data are gathered in a test conducted at the ROCOM (Ros-sendorf Coolant Mixing Model) experimental facility, which reproduceda pump start-up scenario. In addition, to support the interpretation ofexperimental data and system code results, a CFD analysis has been alsoperformed.

The assessment activity includes a comparison with RELAP5-3D© code, aset of sensitivity calculations and the use of the FFTBM package.

Keywords: MARS 3D code assessment, FFTBM

SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEIMUiVi i/. tfR1000071 S

S6-68

RELAP5 Modelling of PWR Reactor RTD Bypass

Resistance Temperature Detectors (RTDs) are used for measurement ofcoolant temperature in primary system of PWR reactor. There are twopossible configurations for realization of that measurement: first has RTDembedded in thermowell structure as part of pipe wall and second re-quires separate small piping to divert part of the coolant flow to manifoldwhere RTD is located (usually known as RTD bypass). Both approacheshave benefits and drawbacks. From point of modeling, using thermal-hy-draulic system codes, first situation is simpler and requires simple modelof thermal inertia for additional metal mass attached to RTD. In secondsituation, detailed model of connecting pipes is required what can causemodeling problems due to needed additional data, small pipes diameterand need for estimation of pressure drops. In this paper, the develop-ment of RTD bypass model is shown using NPP Krško as an example. Themodel is added to existing NPP Krško Relap5/mod3.3 nodalization. The

transient calculations are performed to show behavior of the RTD bypass lines and corresponding tem-perature response. The behavior of the model is studied during and after RCP trip in more detail to showwhy that kind of measurement is not reliable/usable in that case.

Keywords: RTD bypass, NPP Krško, Relap5/mod3.3, RCS temperature measurement

DAVOR GRGIĆ,VESNA BENČIK,SINIŠA ŠADEK,NIKOLA ČAVLINAUniversity of Zagreb, Facultyof Electrical Engineering andComputingUnska 3,10000 Zagreb,Croatiadavor.grgic@fer.hr,vesna.bencik@fer.hr,sinisa.sadek@fer.hr,nikola.cavlina@fer.hr

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SESSION 6: Nuclear Safety Analyses (NSA) 81

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MV-.lliU.V- HR.1;OOOO72R!lJ5Jo

Ujj S6-82

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On the Screening of Other External Events: Explosions andHazardous Release Evaluation

Z D E N K O ŠIMIĆ, Wider scope of external events assessment is considering also evaluationsVLADIMIR M I K U L I Č I Ć of explosions and hazardous chemical release postulated to occur on sitesUniversity of Zagreb, Faculty o r n e a r nuclear power plants. This is potentially important because itof Electrical Engineering and should not affect capability of main control room operators to operateComputing nuclear power plant under the conditions after such events. Major poten-Unska 3,10000 Zagreb, Croatia tial source of these danger is from the outside the plant. Namely they arezdenko.simic@fer.hr either industry facilities or transportation near the site.vladimir.mikulicic@fer.hr T h i g p a p e r ^ d i s c u s s i n g t h e a p p i i c a t i o n of t h e approach defined by the

U.S. Nuclear Regulatory Commission defined in the Regulatory Guide1.78 "Evaluating Power Plant Control Room During a Postulated Hazardous Chemical Release" and 1.91"Evaluations of explosions postulated to occur on transportation routes near nuclear power plants".In the paper most of the screening criteria from the RG 1.78 and 1.91 are applied, and some of necessarysimulations are illustrated. Influence of the various assumptions, and differences in the results betweensimplified calculations and simulations is also investigated.Presented results are illustrating screening process and need for improved guidelines. Based on per-formed analysis it could be concluded that there is further potential to make guidelines more practicalwith provided analysis examples for selected dangerous goods and conditions.

Keywords: PSA, other external events, transportation accidents, screening, explosion, hazard releases

DO SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEI)iUM LLilHRji 0 0 0 0 7 3 -. c:

S6-116

Intermediate Leg SBLOCA - Long LastingPressure Transient

The basic phenomenology of Small Break Loss of Coolant Accident(SBLOCA) for PWR plant is described with focus on analysis of scenarioin which reactor coolant pressure decreases below secondary system pres-sure. Best estimate light water reactor transient analysis code RELAP5/mod3.3 was used in calculation. Rather detailed model of the plant wasused. The break occurs in intermediate leg on lowest elevation near pumpsuction. The size of the break is chosen to be small enough to cause cy-cling of safety valves (SVs) on steam generators (SGs) for some time, but,afterwards, it is large enough to remove decay heat through the break,causing cooling the secondary side. In this case of SBLOCA, when pri-mary pressure decreases below secondary pressure, long lasting pressure

transients with significant amplitude occur. Reasons for such behaviour are explained.

Keywords: RELAP5, Loss of Coolant Accident (LOCA), repressurization, ECCS injection, rod temperature,two-phase flow, core level, core cooling, natural circulation, loop sealing

DAMIR KONJAREK,TOMISLAV BAJS,JOSIP VUKOVIĆENCONET d.o.o.Miramarska 20,10000 Zagreb,Croatiadamir.konjarek@enconet.hr,tomislav.bajs@enconet.hr,josip.vukovic@enconet.hr

§fn3

SESSION 6: Nuclear Safety Analyses (NSA) Q'J

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND i.U-.iJiUM iMRI 00.0074ir.DS

2U:* S6-120E| Safety Requirements for New NuclearS Facilitieso

T. B l u e ZABRIC AS a response to renewed interest in the development of nuclear energyINKO Consulting capacity across the globe, vendors are designing new reactors to meet theKolezijska 5A, Ljubljana, growing demand for safer and more economical nuclear power genera-Slovenia tion. Several Europen countries that are preparing for or already commit-inko@siol.net ted to build new NPPs has developed or are developing natonal safety

requirements for new nuclear power plant, mostly referenced on IAEASafety Requirements.

The national regulations cover new features such as improvement of the reliability of safety systems,incorporation of passive safety systems, increased use of computer systems, design enhancements to pro-vide greater protection for external events, plant features/systems for mitigating severe accidents, etc.

This article provides with picture on the safety requirements/criteria for new built defined in the IAEAstandards, USNRC requirements and in the selected European countries: Finland, UK, France (eitheralready specified in the national regulations or expected).

Keywords: IAEA Safety Requirements, new NPPs

SESSION 6: Nuclear Safety Analyses (NSA)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

Session 7 JFReactor Physics and Nuclear Fuel Cycle (RPNFC) |

Dc33

S7-47 S. MICHALEK, G. FARKAS, J. LIPKA, J. RATAJ, J. HAŠČIK, V. SLUGEN, QS. ŠTEVO, A. KOLROS I

5'Determination of Effective Delayed Neutron Fraction forNuclear Reactors 86

S7-53 B. PETROVIC, L. M. HUANGMinor Actinide Burn in Thermal Spectrum withEnhanced Moderation 88

S7-54 M. KROMAR, B. KURINČIČ

Cycle Power Characteristics of the NPP Krško Fuel 89S7-65 D. PEVEC, K. TRONTL, D. GRGIĆ, R. JEČMENICA, M. MATIJEVIĆ,

T. BELAVIĆ

Upgrade of the FUM ACS 2005 Code Package 90S7-66 J. VuKOvić, D. GRGIĆ, D. KONJAREK

ORIGEN2.1 Cycle Specific Calculation of Krško Nuclear PowerPlant Decay Heat and Core Inventory 91

S7-79 R. JEČMENICA, D. GRGIĆ, D. PEVEC

Prediction Capabilities of Spectral Codes DRAGON,FA2D, and NEWT 92

SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC) Q C

.3 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND 1*\Vm\Il': ; H R 1 00.0 0,75=; i ;s

U

c2

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o(N

S7-47

Determination of Effective Delayed Neutron Fractionfor Nuclear Reactors

o JAN HAŠČIK,SVETOZAR MlCHALEK,GABRIEL FARKAS,VLADIMfR SLUGEN,JOZEF LlPKASlovak University ofTechnology, Faculty ofElectrical Engineering andInformation Technology,Department of Nuclear Physicsa technologyIikovičova 3, 812 19 Bratislava,Slovak Republicjan.hascik@stuba.sk,svetozar.michalek@stuba.sk, gabriel.farkas@stuba.sk,vladimir.slugen@stuba.sk,jozef.lipka@stuba.sk

S T A N I S L A V Š T E V O

Slovak University ofTechnology, Faculty ofElectrical Engineering andInformation Technology,Institute of Control andIndustrial InformaticsIikovičova 3, 812 19 Bratislava,Slovak Republicstanislav.stevo@stuba.sk

JAN RATAJ,ANTONIN KOLROSCzech Technical Universityin Prague, Faculty of NuclearSciences and PhysicalEngineering,

Though delayed neutrons constitute only a very small entity of the totalnumber of neutrons generated from fission, they play a dominant role inthe fission chain reaction control. If only the prompt neutrons existed,the reactor operation would become impossible, due to the fast reactorpower changes. Therefore, the exact determination of the value of effec-tive delayed neutron fraction (fieff) is one of the main requirement in thefield of reactor physics. The effective delayed neutron fraction (/J,,̂ ) is themain parameter in reactor dynamics. In the paper, methods of its possibledetermination are summarized and a (3^ calculation for a research reac-tor VR-1 and power reactor VVER-440 using stochastic transport MonteCarlo method is made. Also an experimental method for evaluation of thisparameter for VR1 research reactor using fast periodical reactivity inser-tion is described. Similarly the paper presents possibility of experimentalevaluation of/S^for power rector.

The focus of this paper is in the determination of ji^ for training reactorVR-1 located at CTU in Prague. The major reason of selecting this topiclies in the fact, that this parameter has never been evaluated by calculationor determined by experiment for the new fuel used at the reactor since2005. It has only been estimated empirically, considering the informationabout the reactor-physical properties of the core for the previous type offuel. In 2005, the original fuel with enrichment of 36% had to be replacedby a new one, enriched to less than 20% within the U.S. - Russian non-proliferation program, which could have influenced the current Rvalue .Therefore, the experimental verification of the VR-1 training reactor ac-tual/?^ value is more than required.

The process of /^determination is based on the theory of Linearized re-actor of zero-power. It starts with the continuous development of a meth-odology of/^measurement, continues with performance of several reac-tor measurement series.Another motivation was to examine the application of this methodologyonto a real system, i.e. the VVER-440 power reactor by means of a seriesof measurements performed during the non-standard tests of reactor'sphysical startup.

86 SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

too

Department of Nuclear Additionally, the experimental determination was supported by calcula-Reactors tions using the stochastic MCNP5 code. This type of code was selectedV Holešovičkach 2,180 00 because of the level of experience achieved in its using in our depart-Prague 8, Czech Republic ment. brataj@fjfi.cvut.cz, a-antonin.kolros@fjfi.cvut.cz Keywords: effective delayed neutron fraction (jieff), reactivity, transfer 3

function, genetic algorithm fLn

SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC) Q H

.2 8 m INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ?,<H>! ,.':•.' W R 1 0 0 0 . 0 7 6 V.\o

* S7-53

o

Minor Actinide Burn in Thermal Spectrumwith Enhanced Moderation

BOJAN PETROVIC, Resolving the issue of spent nuclear fuel and nuclear waste managementLLOYD M. HUANG is the necessary condition for long-term sustainability of nuclear power,Georgia Inst. ofTechnology, a n d requires addressing plutonium, minor actinides (MA) and fissionNuclear and Radiological products. Various strategies are being considered, from once-through ho-Engineering, Atlanta, GA mogeneous burn to partitioning and transmutation, and from thermal to30332-0745, USA fast systems. The optimum system-level performance will likely requirebojan.petrovic@gatech.edu advanced critical or subcritical systems with a range of neutron spectra.

Thermal systems, while not optimum, may be deployed sooner, and mayprovide mid-term amelioration of the issue.

This paper examines burning of minor actinides in thermal systems. One specific concern in this case isthe deterioration of safety parameters due to their high thermal absorption cross section causing spec-trum hardening. Enhanced moderation has potential to at least partly remedy this concern. Therefore, wehave evaluated adopting a fuel assembly design with increased lattice pitch to fuel rod diameter ratio.

The IRIS reactor design offers enhanced safety margin, due to its fully passive safety systems and safety-by-design approach. Moreover in addition to the standard UO2 fuel (the reference IRIS design), an alter-native core with enhanced moderation fuel was evaluated. These two features (safety margin, enhancedmoderation) provide a good starting point for minor actinides burn in a thermal system. The paper willexamine the benefit of the enhanced moderation in comparison to homogeneous burning of minor ac-tinides in a typical PWR reactor spectrum.

Keywords: Nuclear fuel cycle, minor actinides burn in thermal reactor, enhanced moderation

g o SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND Ml.DHM L> \lr

L

Cycle Power Characteristics of the NPP Krško Fuel

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MARIAN KROMAR"Joief Stefan" InstituteReactor Physics DivisionJamova 39,1001 Ljubljana,Sloveniamarjan.kromar@ijs.si

BOJAN KURINČIČNPP KrškoVrbina 12, 8270 Krško,Sloveniabojan.kurincic@nek.siInfluence of the assemblies'cycle power distribution on

the grid-to-rod fretting wear is examined for the NPP Krško fuel. Averagepower ratios between the loading cycles and radial burnup gradients arecalculated. It is assumed that these factors could contribute to the forma-tion of the grid-to-rod gap, which can results in the grid-to-rod frettingdamages to the rod cladding. Results of the fuel assemblies with confirmedgrid-to-rod fretting wear are compared with other non leaking assembliesto determine, if there is a particular pattern in the power distribution thatcan contribute to the grid-to-rod fretting. Although all leaking fuel as-semblies were located near the core baffle and operated at relatively lowpower in the last cycle, no other significant correlation between the powerand burnup distribution and the grid-to-rod fretting wear could be con-firmed.

Keywords: PWR, power distribution, damaged fuel, grid-to-rod frettingwear

n

SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC) 89

.2 8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MILUil.-.M F,iHR10.0.0078 EOSoUE

IQ

o

S7-65

Upgrade of the FUMACS 2005 Code Package

oI

VO

DUBRAVKO PEVEC,KREŠIMIR TRONTL,RADOMIR JEČMENICA,MARIO MATIJEVIĆ,DAVORGRGIĆUniversity of Zagreb, Facultyof Electrical Engineering andComputingUnska 3,10000 Zagreb,Croatiadubravko.pevec@fer.hr,kresimir.trontl@fer.hr,radomir.jecmenica@fer.hr,mario.matijevic@fer.hrdavor.grgic@fer.hr

T O M I S L A V B E L A V I Ć

PRONERG d.o.o.Lukoranska 2,10000 Zagreb,Croatiabelavic@pronerg.hr

The FUMACS code package (an acronym of FUel MAnagement CodeSystem) was initially developed at Ruder Bošković Institute in the year1991 with the aim to enable in-core fuel management analysis of the NPPKrško core for nominal (full power) conditions. Following NPP Krškomodernization process, the new version of the FUMACS code packagewas made in the year 2001 to enable modeling of the NPP Krško corefor uprated conditions and longer cycles. A graphical user interface wasincorporated into the code package to make the code package more userfriendly. The FUMACS code package has also been upgraded in the year2005 to include modeling of integral fuel burnable absorbers (IFBAs) con-taining enriched boron.

Since Westinghouse plans to use next generation fuel (NGF) and integralburnable absorbers containing gadolinium in the following cycles, the ex-isting version of the FUMACS code package would not be able to modelthe NPP Krško core properly. Therefore, the new options for modelingNGF and gadolinium depletion have been introduced into the FUMACScode package. The new, upgraded, FUMACS code package has been veri-fied and validated for NPP Krško preliminary operating cycles.

Keywords: in-core fuel management, FUMACS code package

SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MED!". W Y.V V>:-U - U ^ i 9 : '

S7-66

ORIGEN2.1 Cycle Specific Calculation ofKrško NuclearPower Plant Decay Heat and Core Inventory

JOSIP VUKOVIĆ,DAVOR GRGIĆ,DAMIR KONJAREKENCONET d.o.o.,Miramarska 20, 10000 Zagreb,CroatiaFaculty of ElectricalEngineering and Computing,University of ZagrebUnska 3, 10000 Zagreb,Croatiajosip.vukovic@enconet.hr,davor.grgic@fer.hr, damir.konjarek@enconet.hr

This paper presents ORIGEN2.1 computer code calculation of Krško Nu-clear Power Plant core for Cycle 24. The isotopic inventory, core activityand decay heat are calculated in one run for the entire core using explicitdepletion and decay of each fuel assembly.Separate pre_ori application which was developed is utilized to preparecorresponding ORIGEN2.1 inputs. This application uses information oncore loading pattern to determine fuel assembly specific depletion historyusing 3D burnup which is obtained from related PARCS computer codecalculation. That way both detailed single assembly calculations as well aswhole core inventory calculations are possible. Because of the immenseoutput of the ORIGEN2.1, another application called post_ori is used toretrieve and plot any calculated property on the basis of nuclide, element,summary isotope or group of elements for activation products, actinidesand fission products segments. As one additional possibility, with thepost_ori application it is able to calculate radiotoxicity from calculated

ORIGEN2.1 inventory.

The results which are obtained using the calculation model of ORIGEN2.1 computer code are success-fully compared against corresponding ORIGEN-S computer code results.

Keywords: ORIGEN2.1, core activity, decay heat, fuel depletion, fuel decay, activation products, actinides,fission products, ORIGEN-S, radiotoxicity, prejori, post_ori, burnup

O

33

n3

SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC) 91

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M1DH A • F.iHR'1 OO0O8O-'i-.SoU

Q

o

o

S7-79

Prediction Capabilities of Spectral Codes DRAGON,FA2D, and NEWT

DRAGON is neutron transport code for calculation of pin cells and fuelassemblies developed at Institut de Genie Nucleaire Ecole Polytechniquede Montreal. In our calculations we used the version 4 of this code. FA2Dis 2D transport collision probability code developed at Faculty of Elec-trical Engineering and Computing, University Zagreb and NEWT (asfound in SCALE 6.0) is discrete ordinates transport code developed atOak Ridge National Laboratory. These three codes are used for calcula-tion of NPP Krško 16x16 fuel assemblies without and with IFBAs, for twoU-235 enrichments 4.4% and 4.8%, as found in cycle 24 of the plant. Theheterogeneous depletion calculation was performed up to burnup of 60GWd/tU. The prediction capabilities of the codes are compared for infi-nite multiplication factor, 2-groups homogenized cross section constants,

selected isotope number densities, and for 2D pin power form factors. In addition, in case of DRAGONcode, the influence of different used neutron data libraries (WLUP based 69-groups libraries were used)was studied.

Keywords: group cross section constants, depletion calculation

RADOMIR JEČMENICA,DAVOR GRGIĆ,DUBRAVKO PEVECFaculty of ElectricalEngineering and Computing,University of ZagrebUnska 3,10000 Zagreb,Croatiaradomir.jecmenica@fer.hr,davor.grgic@fer.hr,dubravko.pevec@fer.hr

n SESSION 7: Reactor Physics and Nuclear Fuel Cycle (RPNFC)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

Session 8 |Radioactive Waste Management and Decommissioning (RWMD) |

a

S8-10 I. B. PLEĆAŠ QO

Mathematical Modelling of Immobilization of Radionuclides 137Cs §and 60Co in Concrete Matrix 94

S8-33 P. ORMAIHungarian Waste Retrieval Program for Enhancingthe Long-Term Safety of the Near Surface Repository 95

S8-42 A. KNAPP, I. LEVANAT, V. LOKNER

Compensations to Local Communities in the Krško NPPDecommissioning Program 96

S8-43 C. GEAMBASU, A.SORESCU

EU Support towards Romania to Get Safe Nuclear Waste Management 97S8-55 I. LEVANAT, V. LOKNER, A. RAPIĆ, M. KRALI, I. MELE, P. STROPNIK,

N. ŽELEZNIK

Revision 2 of the Program of NPP Krško Decommissioningand SF & LILW Disposal 98

SESSION 8: Radioactive Waste management and Decommissioning (RWMD)

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM iiuHFM 0 0 0 0 8 1 ^ SI IU

c88

oCM

S8-10

Mathematical Modelling of Immobilization of Radionuclides137Cs and 60Co in Concrete Matrix

ILIJA B. PLEĆAŠ Transport phenomena involved in the leaching of a radioactive materi-Institute of Nuclear Sciences a^ from a cement composite matrix are investigated using an empirical"Vinca" method employing a polynomial equation. To assess the safety for disposalP.O.Box 522,11001 Belgrade, of radioactive waste-cement composition, the leaching of 137Cs and 60Co,Serbia from a waste composite into a surrounding fluid has been studied. Leach-iplecas@vinca.rs ing tests were carried out in accordance with a method recommended by

IAEA. Determination of retardation factors, KF and coefficients of distri-bution, kj, using a simplified mathematical model for analyzing the migra-

tion of radionuclides, has been developed. Transport phenomena involved in the leaching of a radioac-tive material from a cement composite matrix are investigated using an empirical method employing apolynomial equation. In our experiment we have analized mechanism of 137Cs and 60Co leaching valuesduring a period of 60 days. Results presented in this paper are examples of results obtained in a 25 yearmortar and concrete testing project, which will influence the design of the engineered trenches systemfor a future central Serbian radioactive waste storage center.

Keywords: leaching, retardation factor, immobilization, radioactive waste

1 J SESSION 8: Radioactive Waste management and Decommissioning (RWMD)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME7>H,'.V; ; j . i | d R ; 1 0 0 0 0 8 2

S8-33

Hungarian Waste Retrieval Program for Enhancing the Long-TermSafety of the Near Surface Repository

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frPETER O R M A I The Hungarian near surface repository for disposal of institutional ra- QPublic Limited Company dioactive waste has been operating since 1976. Based on the findings of |for Radioactive Waste the safety assessments, corrective actions have to be applied in order toManagement (PURAM) ensure post-closure safety. Since the free capacity of the repository has2040, Budaors, Puskas T. 11, run short, an additional task beside the safety enhancement measures isHungary to provide free capacity within the existing facility. Both types of opera-ormai.peter@hk.hu tions would require the opening of the vaults that are already temporarily

sealed and covered. At first a trial project was performed with an aim todemonstrate the feasibility of the safety enhancement procedures. Started

in April 2007, content of four concrete vaults were processed. The measures included retrieval of wastefrom the disposal vault, sorting out the safety critical items, putting them into interim store after con-ditioning or repackage. Before re-disposal of the waste free from long-lived nuclides, volume reduction,repackaging and detailed characterization were carried out. The paper provides the experiences of thewaste recovery project.

Keywords: radioactive waste, institutional waste, repository, safety enhancement

SESSION 8: Radioactive Waste management and Decommissioning (RWMD) Q r

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M^ULUr-i EiHR1;Oj00083iDSoU* S8-42

2-§Q

o

Compensations to Local Communities in the Krško NPPDecommissioning Program

IVICA LEVANAT, ALEMKA In Slovenia, direct financial compensations (for "limited land use") toK N A P P local communities hosting nuclear facilities were initially specified by aPolytechnic of Zagreb government Decree from 2003. In Croatia, a possibility of direct financialVrbik 8,10000 Zagreb, Croatia compensations had been indicated in the land use plan in conjunctionivica.levanat@tvz.hr, alemka. with the prospective RW repository siting about a decade earlier, but theknapp@tvz.hr topic was subsequently abandoned together with the repository project.VLADIMIR LOKNER *n ^004, the joint Slovenian-Croatian Decommissioning and LILWand SF

management program for NPP Krško from 2004 (the 1st revision of the' joint Program) conservatively included the compensation amounts from

c • ' the Slovenian Decree into the cost estimates of LILW and SF repositories,vladimir.lokner@apo.hr although their location was entirely unspecified ("in Slovenia or in Croa-

tia").

Shortly before the 2nd revision of the joint Program started in the fall of2008, the Slovenian government had amended its Decree, practically doubling the amounts of the reposi-tory compensations. Assuming that some (or possibly all) nuclear facilities and waste, dealt with in theProgram, may be located in Slovenia, the revision has adopted a conservative approach to include allcompensations to local communities that may be required by the Slovenian regulations into the Programcosts.

This paper discusses the Slovenian government Decree, its impact on the joint Program costs, and itsimplications on RW and SF management in the region.

The Decree suffers from the lack of self-consistency, clarity, and consistency with the more general legalprovisions on which it should have been based, but it may have an important supporting role in the pro-cess of RW and SF management facilities siting. The Decree introduced significant additional costs intothe joint Program, which have grown from about one hundred million euro in the 1st revision to about halfa billion in this revision (depending on the Program scenario). Besides, application of the Decree in thejoint Program has set a precedent, after which it would be difficult to imagine that any future RW or SFmanagement facilities in Slovenia or in Croatia could be established without direct financial compensa-tions to local communities in similar or higher amount.

Keywords: RW repository, NPP Krško decommissioning, compensations to local community

SESSION 8: Radioactive Waste management and Decommissioning (RWMD) •

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M Y',;i> >i\'. J

S8-43

EU Support towards Romania to Get SafeNuclear Waste Management

ocCccr

European Union's programs continue to provide assistance to Romaniafor accelerating and completing the safe nuclear waste management.

The sources of radioactive waste in Romania are users of radiation andradioactive materials in industry, including nuclear electricity generation,back-end nuclear fuel cycle activities and decommissioning, the operationof research reactors, the use of radiation and radioactive material in medi-cine, agriculture, industry and research, processing of material containingnatural radionuclides.

At this moment, in Romania there is a single repository for disposal ofradioactive waste: National Repository for Low and Intermediate Radio-active Waste (undergoing a modernisation process) - Baita, Bihor county,sited in Apuseni mountains.

With EU assistance, ANDRAD has in view the achievement of a finalrepository for low and medium level waste which will be operational by2014 and will be situated in the Saligny site (Dobrogea area).

This paper presents the current status of the activities carried on in order to complete the safe nuclearwaste management storage in Romania, with assistance from the EU.

Keywords: radioactive waste management, repository

CRISTIANA GEAMBA§U

Authority for Coordination ofStructural InstrumentsMinistry of Public Finance44 Mircea Voda, sector 3,030664 Bucharest, Romaniacristiana_geambasu@yahoo.com

A N T O N I U S

G H E O R G H E - S O R E S C U

Nuclear Agency &RadioactiveWaste21-25 Mendeleev str., sectorl,010362 Bucharest, Romaniaantonius.sorescu@andrad.ro

7?

n

SESSION 8: Radioactive Waste management and Decommissioning (RWMD) Q*7

y: 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME.M; V i L.HRil^0,000,85)!;

S8-55

Revision 2 of the Program of NPP Krško Decommissioningand SF & LILW Disposal

3(N IVICA LEVANAT,

VLADIMIR LOKNER,ANDREA RAPIĆ

APOLtd.Savska 41/IV, 10 000 Zagreb,Croatiavladimir.lokner@apo.hr

M E T K A KRALJ,IRENA M E L E ,P R I M O Ž STROPNIK,NADJA ŽELEZNIK

ARAO

Parmova 53, Ljubljana,Slovenianadja.zeleznik@gov.si

First joint Slovenian-Croatian Program of NPP Krško Decommissioningand SF & LILW Disposal (DP) was completed in 2004 and formally adopt-ed in 2005. As bilateral agreement on the NPP requires periodic revisionsat least each 5 years, revision 2 of DP was started in September 2008, withthe purpose to incorporate relevant developments since the 1st revision, toimprove the level of details and reliability of DP, and to propose updatedand more accurate cost estimates and appropriate financing models.In the first phase of the revision, new supporting studies for DP moduleswere prepared. Among these studies, the most demanding was the NPPKrško specific Preliminary Decommissioning Plan (PDP), complying withthe IAEA-recommended format, which included development of the NPPdecommissioning inventory database. For upgrade of SF management,new and more detailed descriptions with improved cost estimates wereprepared. Update of LILW disposal concept was based on new develop-ments and projects prepared for the Slovenian repository.In the second phase of the revision, integrated DP scenarios were formu-lated and analyzed. They integrate NPP decommissioning together with

RW and SF management/disposal into rationally inter-related sequences. Boundary conditions for thisrevision required: (a) that the reference scenario from the previous revision should be re-examined, withappropriate variations or new alternatives; (b) that the option of the NPP Krško life extension should alsobe included; and (c) that the possibility of diverging interests of the contracting parties should also beanalyzed (i.e. waste division and separate management).

Finally, scenario evaluation is intended to compare the analyzed scenarios taking into account both theirfeasibility and estimated costs. It should provide the basis for determining future financing of DP, namelythe annuities to be paid by the NPP Krško owners into the national decommissioning funds.

Keywords: NPP Krško decommissioning, LILW repository, SF management

98 SESSION 8: Radioactive Waste management and Decommissioning (RWMD)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

Session 9Public Relations (PR) §

S9-16 N. ŽELEZNIK Qo

Mental Models of Radioactivity and Attitudes towards §Radioactive Waste 100

S9-62 1. JENČIČTangible Results of Nuclear Information Centre in Slovenia 101

S9-64 K. TRONTL, R. JEČMENICA, D. PEVEC

Public Opinion Survey - Energy - The Present andthe Future - 2009/10 102

SESSION 9: Public Relations (PR) QQ

.2 8TH INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND Mf.iJil-'.. \- - 7 . ^ ' 9 c i 9 9 t$ i -JS

SU^ S9-16co

|

oCN

Mental Models of Radioactivity and Attitudes towardsRadioactive Waste

g NADJA ŽELEZNIK Siting of a radioactive waste repository presents a great problem in almostvi /47?J4O every country that produces such waste. The main problem is not a technical^ Parmova 53, Ljubljana, one> but socio-psychological, namely the acceptability of this kind of reposito-

Slovenia ry. Previous research on people s perception of the LILW repository construc-nadja.zeleznik@gov.si tion, their attitudes towards radioactive waste, their willingness to accept it,

indicated significant differences in answers of experts and lay persons, mainlyregarding evaluation of the consequences of repository construction.

Based on the findings of pilot investigations a mental model approach to the radioactivity, radioactivewaste and repository was used as a method for development better risk communication strategies withlocal communities. The mental models were obtained by adjustment of the method developed by Mor-gan and co-workers where expert model of radioactivity is compared with mental model of lay peopleobtained through individual opened interviews. Additional information on trust, risk perception, role ofmain actors in the site selection process and their credibility was gained with the overall questionnaire onthe representative sample of Slovenian population.

Results of the survey confirm some already known findings, in addition we gained new cognitions and withanalyses obtained the relationships and ratios between different factors, which are characteristics both forthe general public and for the public, which is involved in the site selection process for a longer period andhas been living beside a nuclear power plant for one generation. People have in general negative associationsregarding the repository, the perceived risk for nuclear facilities is high, and trust in representatives of gov-ernmental institutions is low. Mental models of radioactivity, radioactive waste and the LILW repository aremostly irregular and differ from the experts' models. This is particularly valid for the models of radioactivityand the influences of radiation on people irrespective of the public which was involved in the survey. Amongthe most important factors which influence public acceptability of the construction of the LILW repositoryin the domestic location is perceived risk to the nuclear power plant. This factor is more important thanknowledge on radioactivity and radioactive waste for different groups, also for the local public with experi-ence of living beside nuclear power plant. Although it can be seen that the factor of knowledge has higherimportance in the local community which means that communication activities among local citizens doinfluence the acceptability. Based on the analyses of the results, the starting points for improvement of com-munication plans were prepared, which should be used by the implementer of the site selection, and laterduring the repository construction. These communication starting points have a broader validity, since theycould be suitable also for risk communications for other technologies.

Keywords: mental models, acceptability, radioactive waste, repository, perceived risk, knowledge, trust

nn SESSION 9: Public Relations (PR)

8T H INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND tyEDlGK: P,HRi1;QPP087:

S9-62

Tangible Results of Nuclear InformationCentre in Slovenia

sc

oIGOR JENČIČ Nuclear Training Centre Ljubljana was established in 1989 and a few years oJožef Stefan Institute later its activity expanded from pure professional training to public infor-Nuclear Training Centre mation, as well. The goal was to achieve better social acceptance of nucle-Jamova 39,1000 Ljubljana, ar power in Slovenia which was very low in early 1990s. We focused onSlovenia schoolchildren and other organized groups and since then we had moreigor.jencic@ijs.si than 120,000 visitors. The mainstays of our activity are a live lecture and a

permanent exhibition. In the recent years the Nuclear Information Centreand its web site www.icjt.org has also become a respected source of infor-

mation for the media and the general public.

In the first few years it was quite hard to notice any improvement in public attitude and even later, whennuclear power became less controversial, it was difficult to link this change to the activities of the NuclearInformation Centre.

Recently, however, several independent polls on a representative sample of general population provedthat in a long term, our activities did have tangible results and that Nuclear Information Centre as part ofJožef Stefan Institute is regarded as trusted source of information.

An Eurobarometer poll showed that Slovenia ranked among the first three countries in Europe regardingknowledge of nuclear waste issues in Europe. Another poll showed that Jožef Stefan Institute is the mosttrusted institution on radioactive waste issues. A third independent poll showed that the knowledge andthe attitude towards nuclear is most favorable in the youngest age group of general population, i.e., manyof whom have previously visited the Nuclear Information Centre. These are all indications that the activi-ties of the Nuclear Information Centre have contributed to a measurable change in the public opinionand knowledge of nuclear issues in Slovenia. Furthermore this shows that informing youngsters is a verylong term activity and that first tangible results can only be expected in 15 years or so. On the other hand,however, informing youngsters penetrates the society in a very broad manner and thus makes it less sus-ceptible to superficial claims of antinuclear activists.

Keywords: public information, opinion polls

SESSION 9: Public Relations (PR) 1 Q 1

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND M.'-Oil -^ H H R 1 0 0 0 0 8 8 ! f ;

a2uc2

QPublic Opinion Survey - Energy - The Presentand the Future - 2009/10

S9-64

o KREŠIMIR TRONTL,RADOMIR JEČMENICA,DUBRAVKO PEVEC

University of Zagreb, Facultyof Electrical Engineering andComputing, Department ofApplied PhysicsUnska 3,10000 Zagreb, Croatiakresimir.trontl@fer.hr,radomir.jecmenica@fer.hr,dubravko.pevec@fer.hr

During the academic year 2009/10 the Department of Applied Physics ofthe Faculty of Electrical Engineering and Computing conducted a publicopinion survey entitled "Energy - The Present and the Future" amongstudent population of 622 individuals age 18-20 (413 male students, 202female students, and 7 students without the answer on gender question).The tested population consisted of the University of Zagreb four facul-ties' students: the Faculty of Electrical Engineering and Computing, theFaculty of Food Technology and Biotechnology, the Faculty of ChemicalEngineering and Technology, the Faculty of Civil Engineering. The ques-tions in the survey covered several different energy issues, including thepresent and the future energy resources, the acceptability of different fueltype power plants, the environmental protection and global warming, the

radioactivity, the waste issues, as well as reliable information sources. The basic results of survey analysisfor nuclear oriented questions, as well as the comparison of results of the current survey with the resultsof the similar survey conducted in the academic year 2007/08, are reported in this paper.Participants generally express high level of formal environmental awareness. However, their choices andattitudes are in a contradiction to claimed eco-orientation, as well as to the scientific facts. The discrep-ancies are particularly noticeable in parts of the survey dealing with the nuclear energy and the nuclearpower plants. The participants are also demonstrating lack of knowledge on nuclear issues especiallyregarding radioactive waste management, as well as economics and operational safety of nuclear powerplants.

Keywords: public opinion survey, energy, nuclear energy

02 SESSION 9: Public Relations (PR)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

Session 10 IRegulatory Practice and General Papers (RPGP) to

oO

o35c

SlO-l8 N. NOVOSEL, L. ROSANDIĆ Qo

International Cooperation of the Republic of Croatia in the §Field of Nuclear Safety 104

S10-27 Z. BAZSO

Regulatory Aspect of Periodic Safety Review Performedin Nuclear Power Plants in the Slovak Republic 105

S10-83 S. PLESLIĆ

Implementation of Knowledge Management inR&D Institutions 106

SESSION 10: Regulatory Practice and General Papers (RPGP)

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND ME OiU.Vi Vrt _oU.* S10-18cS

Q

o

International Cooperation of the Republic of Croatiain the Field of Nuclear Safety

g NEVENKA NOVOSEL, International cooperation of the Republic of Croatia in the field of nuclearJ, LUCIJA ROSANDIĆ safety can be divided in two parts - political part, for which the Ministry"* State Office for Nuclear Safety °f Foreign Affairs and European Integration is responsible, and technical

Ulica grada Vukovara 284, Part> f° r which the State Office for Nuclear Safety is responsible, in coop-10000 Zagreb, Croatia eration with other state administration bodies, where applicable.nevenka.novosel@dzns.hr, According to the Nuclear Safety Act (OG 73/2003) the State Office forlucija.rosandic@dzns.hr Nuclear Safety: "coordinates technical cooperation with the International

Atomic Energy Agency for all participants from the Republic of Croatia";"fulfills the obligations which the Republic of Croatia has assumed through international conventions andbilateral agreements concerning nuclear safety and the application of protective measures aimed at thenon-proliferation of nuclear weapons" and "cooperates with international organizations and associationsin the area of nuclear safety, and appoints its own expert representatives to take part in the work of suchorganizations and associations or to monitor their work"In this paper various aspects of the technical cooperation with the International Atomic Energy Agency,as well as international conventions and bilateral agreements in the field of nuclear safety, will be present-ed. Also, cooperation with other international organizations and associations in the nuclear area, such asNuclear Suppliers Group, Zangger Committee, Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, will be described.

Keywords: international cooperation, nuclear safety, conventions, agreements, international organiza-tions

(\A SESSION 10: Regulatory Practice and General Papers (RPGP)

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND Mbcilr/; !::HR!PPPP?,P

S10-27g

Regulatory Aspect of Periodic Safety Review Performed |in Nuclear Power Plants in the Slovak Republic 5?

ZoLTAN BAZSO The paper deals with the regulatory aspect of Nuclear Power Plant (NPP) QNuclear Regulatory Authority Periodic Safety Review (PSR) as a part of license renewal process in the g.of the Slovak Republic Slovak Republic. It summarizes the history of activities similar to PSROkružna 5, 917 01 Trnava, performed in the past for NPPs operated in the Slovak Republic. Further-Slovak Republic more, it describes both the requirements involved in the current Slovakzoltan.bazso@ujd.gov.sk legislation to be met by licensee in the Slovak Republic in this field and the

procedures concerning the PSR as well.

The objectives and rules of PSR to be performed for NPPs in the Slovak Republic were derived from theinternationally accepted International Atomic Energy Agency (IAEA) document and have been imple-mented into national legislation.

PSR of two twin units located in Bohunice NPP and Mochovce NPP, respectively, has been initiated in theSlovak Republic based on evaluation of each area to be reviewed (safety factors) using recent methodol-ogy and practice. Safety factors, such as ageing, modifications of NPP and the safe operation for a speci-fied future period, have to be assessed in the frame of PSR.

Report on performed PSR outlines the results of review for each area, the corrective plan, which consid-ering mutual relations between assessed areas specifies the issues to be solved with the aim to eliminateshortcomings identified in the frame of PSR and to adopt safety improvements. The findings from PSR inthe evaluated areas also serve as a source of information for updating of all documents to be attached tothe written application of licensee for renewal of a nuclear power plant operating license.

The presented procedure describes how the Nuclear Regulatory Authority of the Slovak Republic (UJDSR) has reviewed the documents submitted during PSR. Based on results of submitted documents evalu-ation and licensee application for license renewal the license for next 10 years operation has been issuedfor Bohunice NPP (V2 NPP). At present, similar procedure for Mochovce NPP unit 1 and 2 (Mochovce 1& 2 NPP) is underway.

Keywords: regulatory body, nuclear power plant, power uprate, licensing process

SESSION 10: Regulatory Practice and General Papers(RPGP) 1 n / r

.2 8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND K;;:(,Tu'i\i H R 4 O 0 O 0 9 1 J ' " ' n < L ;

aOU

c2

•§Q

o

S10-83

Implementation of Knowledge Managementin R&D Institutions

o SANDA PLESLIĆUniversity of ZagrebFaculty of ElectricalEngineering and ComputingDepartment of Applied PhysicsUnska 3,10000 Zagreb, Croatiasanda.pleslic@fer.hr

Knowledge could be considered as the strategic key resource for the 21 s t

century. Utilization of knowledge is a base for decision making processes.Knowledge management is an approach that many R&D organizationsor institutions use to deal with knowledge but the success of knowledgemanagement depends mainly on understanding and supporting the user'sneed to know. Implementation of knowledge management has to be basedon a concrete definition of knowledge management. The main problemcomes from different perspectives. So, all features of knowledge man-agement should be used as a base for knowledge management definition

and, later, knowledge management implementation. Some of these features are: description of knowl-edge management as a performance of knowledge processes, association of knowledge management withthe institutional objectives, connection of knowledge management with institutional processes, orien-tation of knowledge management activities to greater competitiveness, productivity and effectiveness,link of knowledge management with information and communication technologies, and, finally, relationof knowledge management with decision making. A general methodology of knowledge managementimplementation in R&D institutions is very hard to find and to apply. It leads to particular efforts of indi-vidual institutions to develop their own methodology depending on their own needs and objectives.

Keywords: knowledge management, implementation, R&D institutions

SESSION 10: Regulatory Practice and General Papers (RPGP)

1 INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS £i

Index of Authorstoo

Dccr

Adorni, Martina, 74Agosteo, Stefano, 43Ahn, Seung Hoon, 80Allison, Chris, 75Andročec, Ivan, 29Androjna, Andrej, 68Antolovič, Aleksandra, 78

B

Bajs, Tomislav, 54, 83Balić, Matija, 54Bašić, Ivica, 54, 77, 78Baurski, Jacek, 26Bazso, Zoltan, 105Belavić, Tomislav, 90Benćfk, Marek, 74Benčik, Vesna, 81Bergroth, Nici, 36Bertalanić, Zoran, 62Bilić Zabric, T., 84Birchley, J., 75Bišćan, Romeo, 65Bituh, Tomislav, 42Bošnjak, Darjan, 53Božin, Bojan, 67Broggio, David, 43Bronnikov, V., 23

Budulan, Pompiliu, 49

Burn, Kenneth W., 37

Carelli, Mario, 37

Carlan, Loic Lenoir De, 43

Casalini, Lodovico, 37

Cerovac, Zdravko, 41

Cherubini, Marco, 79, 80

Cho, Yong-Jin, 80

Cicvarić, Darko, 48

Ciotti, Marco, 37

Cloete, Chris E., 35

čČavlina, Nikola, 25, 81

Čižmek, Ankica, 64

Ćurković, Ante, 29

D

Debrecin, Nenad, 76Del Nevo, Alessandro, 74, 79Djetelić, Nenad, 54, 55Dudaš, Mladen, 61

n

cr.

Elkin, llya V., 74

Farkas, Gabriel, 86Filipov, Kalin, 73Franceschini, Fausto, 37Franjić, Hrvoje, 50, 51, 52

D'Auria, Francesco, 74, 79, 80

Gaio, Paolo, 34

Galošić, Sergio, 52

Gargioni, E., 43

Geambasu, Cristiana, 97

Gheorghe-Sorescu, Antonius, 97

Glaser, Bruno, 44

Gomez-Ros, J. M., 43

Gracin, Renato, 60

Grgić, Davor, 76, 81,90, 91, 92

Grosswendt, B., 43

109

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS

U

c23

Q

>

Io

Gualdrini, G., 43

H

Hartmangruber, David, 37

Hašči'k, Jan, 86

Hoehne, Thomas, 80

Hohorst, Judith, 75

Huang, Lloyd M., 88

Huet, Christelle, 43

JJakić, Irena, 31

Jarnjak, Fran, 50, 57

Ječmenica, Radomir, 90, 92,102

Jenčič, Igor, 101

Johnson, Jeffrey, 37

K

Kavšek, Darko, 47,67,69

Kirchsteiger, Christian, 19

Knapp, Alemka, 96

Knapp, Vladimir, 28

Kodeli, Ivan, 43

Kolros, Antonin, 86

Konjarek, Damir, 83,91

Kralj, Metka, 98

Kromar, Marjan, 89

Kurinčič, Bojan, 89

Kušar, Ana, 69

Kuzle, Igor, 53

Kuznetsov, Yury N., 39

Lebegner, Josip, 25, 31Levanat, Ivica, 96, 98Lipka, Jozef, 86Litvinsky, L., 23Lokner, Vladimir, 96, 98Lombardi, Carlo, 37Lovrenčič, Peter, 47

M

Malherbe, Johan B., 35Maljković, Zlatko, 62Manchev, Bogomil, 66Mandić, Damir, 58Markulin, Krunoslav, 50, 51, 52Marović, Gordana, 41, 42Matijević, Mario, 28, 90Matoković, Alojzije, 51Matteoli, Camilla, 79Mauna, Traian, 72McKillop, Jordan, 37Mele, Irena, 98Melikhov, Oleg I., 74Meštrović, Tomislav, 41, 42Michalek, Svetozar, 86Mihalina, Mario, 44, 55Mikuličić, Vladimir, 82Moretti, Fabio, 80

N

Nevo, Alessandro Dei, 74

Novaković, Mladen, 41

Novosel, Nevenka, 104

oOrmai, Peter, 95

Pajnić, Mladen, 50, 51, 52

Pandžić, Hrvoje, 53

Pašičko, Robert, 27

Pavlica, Milutin, 62

Perović, Nino, 31

Petrovic, Bojan, 37, 88

Pevec, Dubravko, 28,90,92, 102Philipov, Svetlin, 73

Picek, Edo, 57Plećaš, Ilija B., 94

Pleslić, Sanda, 106Price, R., 43

Prlić, Ivica, 41, 42Purtov, C , 23

R

Nacci, Giulia, 79

Nenkova, Boyka, 66

Rapić, Andrea, 98

Rašeta, Davor, 25

Rataj, Jan, 86

Reitsma, Sebastiaan M. S., 21

Rešković, Šaša, 57

Rollet, Sofia, 43

Rosandić, Lucija, 104

8™ INTERNATIONAL CONFERENCE: NUCLEAR OPTION IN COUNTRIES WITH SMALL AND MEDIUM ELECTRICITY GRIDS

Rožman, Ambroz, 68

Sarotto, Massimo, 37

Schekoldin, Vladimir I., 74

Schumann, Peter, 56

Sejvar, Jim, 37

Sember, Bogoljub, 54

Siebert, B. R. L., 43

Siefken, Larry, 75

Silchenko, S., 23

Skoko, Božena, 42

Slugen, Vladimir, 86

Smoljkić, Gabrijel, 50

Spitaler, Ewald, 42

Stošić, Zoran V, 33

Stropnik, Primož, 98

Struelens, L., 43

Surić Mihić, Marija, 41, 42

Šadek, Siniša, 76, 81Šimić, Zdenko, 82Števo, Stanislav, 86

Turk, Rajka, 42Tyobeka, Bismark M., 18

V

Vavrouš, Matija, 60Vincke, Helmut, 43Vlasenko, N., 23Vrbanić, Ivan, 54, 77, 78Vučajnk, Aleš, 50Vučić, Zlatko, 42Vujec, Nataša, 20Vuković, Igor, 77Vuković, Josip, 83, 91

W

Wiegel, Burkhard, 43

Zaitsev, Sergey I., 74Zakutaev, Maxim O., 74Zankl, M., 43Zilavy, Mark James, 58

ON

Itoo

too

oco"o35rno

Tanner, Rick, 43

Tarnik, Tamara, 29

Tomov, Emil, 66

Tomšić, Željko, 27

Trontl, Krešimir, 90,102

Železnik, Nadja, 98,100

111

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ISBN 978-953-55224-3-0