FUMEX 2 IAEA Coordinated Research Programme Nuclear Fuel Cycle and Material Section

Transcription

1 FUMEX 2 IAEA Coordinated Research Programme Nuclear Fuel Cycle and Material Section

2 Coordinated Research Projects FUMEX-II The CRP on the Improvement of Models used for Fuel Behaviour Simulation to assist Member States in improving the predictive capabilities of computer codes used in modelling fuel behaviour for extended burn-up started at its 1 st RCM, Vienna, December Organizations from 16 countries, the European Commission and the OECD/NEA are participating in the project.

3 Collaborations Joint OECD/NEA IAEA International Fuel Performance Experiment (IFPE) Database: In conjunction with FUMEX-II CRP, histories for more than 300 WWER-1000 high burn-up fuel rods were prepared and added to the IFPE Database. PIE data from RIAR, Russia Calculated power histories from VNNINM, Russia Peer review by INRNI, Bulgaria

4 FUMEX-II Purpose The major objective of the CRP is to improve the predictive capabilities of codes used in fuel behaviour modelling for extended burn-up. The focus is on the topics: Thermal performance Fission gas release Pellet to clad interaction (PCI) at extended burn-up above 50 MWd/kg.

5 FUMEX-II Purpose The major objective of the CRP is to improve the predictive capabilities of codes used in fuel behaviour modelling for extended burn-up. In addition, the CRP address the performance of codes used for transient analysis such as RIA and LOCA at extended burn-up.

6 FUMEX-II FUMEX-II is expected to last some 5 years over the period 2001 to early Within that period, there will be two further meetings of participants: one in 2004 and the final meeting in late 2005/early The final report as a result of the CRP would be completed in 2006.

7 CRP FUMEX-II List of Participants No. Country Name of Chief Scientific Investigator Institute Title of Project 1 Argentina Mr. M. Armando CNEA Improvement of models used for fuel behaviour 2 Belgium Mr. V. Sobolov 3 Bulgaria Mr. D. Elenkov 4 Czech Republic Mr. M. Valach 5 China 6 EC 7 Germany France 8 Korea Republic, of Mr. P. Chen Dr P. van Uffelen Mr. F. Sontheimer Mr.Chan Bock Lee 9 Romania Ms. A. Paraschiv 10 RF Mr. G. Khvostov 11 Canada Mr. M. Tayal 12 India Mr. H.S. Kushwaha 13 UK Mr. T. Turnubull 14 Japan Mr. K. Kamimura 15 Finland Mr. K. Ranta-Puska Nuclear Research Center SCK CEN Institute for Nuclear Research and Nuclear Energy Nuclear Research Institute, Rez China Institute of Atomic Energy JRC Institute for Transuranium Elements FRAMATOME ANP GmbH Korea Atomic Energy Research Institute Institute for Nuclear Research A.A. Bochvar Res. Institute of Inorganic Materials AECL BARC NUPEC VTT Fuel performance modelling at SCK*CEN Improvement of the TRANSURANUS-WWER version code for modelling WWER-fuel performance Validation of fuel performance codes used at the NRI Rez for the Temelin and Dukovany NPPs fuel safety evaluations and operation support Validation of fuel behavior analysis code METEOR/TR by using the data of FUMEX II exercises Application of the TRANSURANUS code in the FUMEX II programme Improvement of high burnup models for fuel temperature and FG release in Framatome ANP fuel rod performance codes Improvement and validation of fuel performance analysis code INERA New methods of evaluation the nuclear oxide fuel behavior Improvement and verification of the START-3 3 code Simulation of FUMEX II data by ELESTRES Code Validation and Improvement of Indian Codes for Fuel Performance for High Burnup Application Qualification of fuel performance codes and datasets Validation of the FEMAXI-JINS code by using PIE data at extended burnup Validation of the ENIGMA fuel performance code

8 CRP FUMEX-II List of Observers Ms S. Stefanova,, INRE Bulgaria: PIN code Mr A. Nordstroem,, PSI, Switzerland: PSI version TRANSURANUS Mr G. Rossiter,, BNFL, UK: ENIGMA-B Mr K. Atkinson, British Energy, UK: ENIGMA

9 FUMEX - II List of high priority cases No. Case identification Measurements made for comparison 3. Halden IFA 597.3, rod 7 Cladding elongation, at Bu 60 MWd/kgUO 2 4. Halden IFA 597.3, rod 8 FCT, FGR at Bu 60 MWd/kgUO 2 7. REGATE FGR and cladding diameter during and after a transient at Bu 47 MWd/kg 14. Riso-3 AN3 FGR and pressure-eol, FCT, Bu 37 MWd/kgUO Riso-3 AN4 FGR and pressure-eol, FCT, Bu 37 MWd/kgUO 2 27 Simplified case (1) Temperature vs Bu for onset of FGR (2a) FGR for constant 15 kw/m to 100 MWd/kgU (2b) FGR for 20 kw/m at BOL decreasing linearly to 10 kw/m at 100 MWd/kgU (2c) FGR for idealized history supplied by BNFL (2d) FGR for idealized history supplied by FANP (3a) FGR for CANDU idealized history (3b) FGR for CANDU idealized history

10 FUMEX - II Joint OECD/NEA IAEA International Fuel Performance Experiment (IFPE) Database: It is planned to obtain a further set of WWER-1000 high burn-up fuel rods for inclusion into the Joint IFPE Database. PIE data from RIAR, Russia Calculated power histories from VNNINM, Russia Peer review done by INRNI, Bulgaria

11 FUMEX - II Progress FUMEX 2 Case 27 Investigator a2b2c2d3a 3b Argentina Belgium x x x x x Bulgaria x x X X x x Canada China Czech x x x EEC Transuranus Finland France India (x) Japan t t t Korea t x x x Romania Russia x x x Bulgaria (SVS) Switzerland t Temperatures only, no FGR result

12 FUMEX - II Programme End date: June 2006? Final RCM: November 2005? 2 nd nd RCM: September 2004

13 FUMEX - II Programme 2 nd nd RCM: September 2004 All priority cases completed by all participants Requires: Completion by some before RCM Agreement on format Additional cases?

14 FUMEX - II Programme Final RCM: November 2005 All cases completed by all participants Requires: All cases available Agreement on format

15 Programme March 2004 September 2004 March 2005 FUMEX - II Agree additional cases for September 2004 meeting Consider shortfalls in data and results All cases need to be available All results in! Review results, identify shortfalls