Joint IAEA-EC-GRS-HAEA Regional Workshop on Safety Assessment of Advanced (GEN III+ and GEN IV) and Upgraded Operating Nuclear Power Plants

PROSPECTUS

Project Number & Title:

TC PROJECT RER/9/126Advancing Safety Assessment Capabilities, Harmonizing Safety Assessments and Creating Synergy between Deterministic and Probabilistic Safety Analyses 

Place (City, Country):

Hungarian Atomic Energy Authority (HAEA)Budapest, Hungary

Dates: 7 – 11 May 2012Deadline for Nominations: 30 March 2012

Organizers: The International Atomic Energy Agency (IAEA) in collaboration with the Institute for Energy, EC Joint Research Centre, Petten, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) m.b.H. and Hungarian Atomic Energy Authority (HAEA)

Host Country Organizer:

MACSUGA, GézaHead of departmentDepartment for Technical SupportHungarian Atomic Energy Authority (HAEA)Department for Technical Support4 Fényes Adolf 6761539 Budapest 114Hungary

Tel: 0036 1 4364910Fax: 0036 1 4364909E-mail: macsuga@haea.gov.hu

Language: The workshop will be conducted in English.

Purpose:The purpose of the workshop is to provide information to participants and to share information among participants on the latest international experiences in the area of safety assessment of advanced nuclear power plants as well as

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those which are in operation and have been upgraded. The main topics covered will include:

Current safety requirements on NPP design for advanced and upgraded reactors;

Design safety features of the main types of advanced reactor concepts Advanced Safety Assessment Methodologies

Application of  lessons learned from the safety assessment on GEN III reactors to GEN IVApplicability of conventional NPP safety assessment computer codes for GEN IV safety assessment

Participants will be expected to present their national experiences on the topics for the workshop, outlined in the attached syllabus.

Expected Output(s):

Knowledge shared among participants on the subject of the workshop. The final state-of-the-art workshop report in electronic form will provide summary of presentations, deliberations and conclusions from the workshop.

Scope and Nature:

The workshop will consist of presentations and discussions in working groups. All participating countries are expected to present their national experience/approach related to the subject of the workshop

Background Information:

The overall objective of this project is to enhance and maintain high levels of nuclear safety in Member States by strengthening their capabilities for performing safety assessments of their Nuclear Power Plants.This workshop will contribute towards this objective by providing and exchanging information on specific aspects as outlined under the “Purpose of the workshop”.

Participation: The meeting is open to 20 participants.The target countries are: Armenia, Belarus, Bulgaria, Croatia, Czech Republic, Hungary, Kazakhstan, Lithuania, Poland, Romania, Russian Federation, Serbia, Slovakia, Slovenia, Turkey, Ukraine and Uzbekistan.

Participants’ Qualifications:

The participants should be professional staff members of the regulatory authorities, utilities and design or technical support organizations from the region.

Nomination Procedure:

Nominations should be submitted on the standard IAEA Nomination Form for Meeting/Workshop and National Consultant (available on the IAEA website: http://www.iaea.org/). Completed forms should be endorsed by relevant national authorities and returned to the Agency through the official channels, i.e. the designated National Liaison Office for IAEA Matters.

The completed nomination forms should be sent to the Programme Management Officer for this project, Mr Pavel Yurkin, through IAEA Official Fax (+43-1-26007) or E-Mail (Official.Mail@iaea.org), not later than 30 March 2012. Nominations received after this date or which have not been routed through the established official channels cannot be considered.

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Administrative and Financial Arrangements:

Nominating Governments will be informed in due course of the names of the candidates who have been selected and will, at that time, be given full details of the procedures to be followed with regard to administrative and financial matters.

Selected participants from countries eligible to receive technical assistance will be provided with a round trip economy class air ticket from their home countries to Budapest, Hungary, and a Daily Subsistence Allowance (DSA) at the prevailing UN Rate. Shipment of accumulated meeting materials to the participants' home countries is not the responsibility of the IAEA.

The organizers of the workshop do not accept liability for the payment of any cost or compensation that may arise from damage to or loss of personal property, or from illness, injury, disability or death of a participant while he/she is travelling to and from or attending the meeting, and it is clearly understood that each Government, in nominating participants, undertakes responsibility for such coverage. Governments would be well advised to take out insurance against these risks.

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Joint IAEA-EC-GRS-HAEA Regional Workshop on Safety Assessment of Advanced (GEN III+ and GEN IV) and Upgraded Operating Nuclear Power Plants

HAEA, Budapest, Hungary7 -11 May 2012

SYLLABUS1. Current safety requirements on NPP design for advanced and upgraded reactors;

o IAEA Safety Standardso WENRA New Reactor Safety Objectiveso Generation IV International Forum (GIF) Safety Goals (JRC)

2.Design safety features of the main type of advanced and innovative reactor concepts

o An overview of Generation IV International Forum (GIF) reactor systems development (JRC)o European strategies and priorities for deployment of innovative reactors: Sustainable Nuclear Energy Technology Platform (SNETP) (JRC)o Review of SNETP Technical Working Groups (GRNSPG)o Safety assessment of European Sodium Fast Reactor (SFR) design (JRC) o Safety assessment of European Lead Fast Reactor (ELSY) design (JRC) o Safety assessment of high temperature gas cooled reactors (GRS)

3. Upgrading Operating Nuclear Power Plants

4. Advanced Safety Assessment Methodologies

o GIF Risk and Safety Working Group Integrated Safety Assessment Methodology (JRC)o SNETP Technical Working Groups on the safety of GEN-II/III concepts, cogeneration, and innovative reactors (GRS)o Description and reliability of passive systems (GRNSPG)

5. Application of  lessons learned from the safety assessment on GEN III reactors to GEN IV (GRNSPG, IRSN)

6. Applicability of conventional NPP safety assessment computer codes for GEN IV safety assessment

o Use of MCNP and COBRA coupled computer codes for assessment of advanced and innovative reactor concepts (JRC)

o Usage of the system code ATHLET for the assessment of advanced reactor concepts: application to gas-cooled reactors (GRS)

o Methodologies for uncertainty and sensitivity analysis in thermal hydraulics and neutronics for current and future plants (GRS)

o Applicability of codes used for the assessment of conventional NPPs to advanced reactors (GRNSPG)

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