Active CRPs (SMoRE, ODS, Zr), TM on FR fuels, collaborations with NEA, HOTLAB and ICTP

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1 TWGFPT April 2012 Active CRPs (SMoRE, ODS, Zr), TM on FR fuels, collaborations with NEA, HOTLAB and ICTP IAEA Victor Inozemtsev IAEA International Atomic Energy Agency

2 Incentives for IAEA CRP on Accelerator Simulation and Theoretical Modelling of Radiation Effects (SMoRE) Operating temperature ( C) ITER HTR Materials Thermal Reactor Materials Fast Reactor Materials Radiation dose (dpa) DEMO Fusion Materials Economically driven growth of operational requirements Introduction of new fuels for advanced and innovative nuclear systems Synergies between fission and future fusion power plants Insufficient basic understanding of the nature of radiation damage Nuclear Technology Review, IAEA, Vienna, Onset of FGR calculations Vitanza threshold is the temperature of 1% FGR, and it is experimentally derived up to approximately 40 GWd/tU CRP FUMEX-2, IAEA, Vienna, 2012 Centre temperature (C) Vitanza Burnup (MWd/kgU) IAEA 2

3 CRP SMoRE: objectives, membership and report structure Objectives 1) to enhance simulation capabilities of accelerators for materials testing, and 2) to contribute to better physical understanding of radiation damage 19 members from 15 countries RCM-1 December 2008 in Vienna /IAEA (matrix of materials and methods) RCM-2 June 2010 in Paris / Saclay (new members Japan and RoK, corrections of the work-plans) RCM-3 November 2011 in Vienna (results, conclusions, draft report) Draft report structure Foreword (1 page rationale and background) 1. Introduction (20pages x 4=60pages) 1.1. Fast neutron radiation effects (15pages+references=20pages) 1.2. Accelerator simulation of neutron irradiation damage (15pages+references=20pages) 1.3. Theoretical modelling of radiation effects (15pages +references=20pages) 1.4. Methods of material testing and characterization (15pages +references=20pages) 2. SMoRE results (7+10x18=190pages) 2.1. Summary (short descriptions and collaborations) Member works, with the standard structure: Background, Results (Experiment, Modelling), Discussion, Conclusions, References 3. Discussion (5pages) 4. Conclusions and recommendations (2 pages) Abbreviations (2 pages) List of contributors (2 pages) (Total about 270 pages) IAEA 3

4 CRP SMoRE: contributions by countries 1. Belgium: SCK.CEN (L. Malerba) Fe-Cr potentials, their use in MD and MC, EPA experiments; 2. China: CIAE (Sh. Zhu) CLAM irradiation up to 85 dpa, temp. effects, tripple beam H/He synergy; 3. France: CEA (F. Willaime), EdF (G. Monnet) MSM in Fe, Fe-Cr, ODS, Jannus tripple beam, DD; 4. India: BARC (P. V. Durgaprasad) MD, DD in Fe, Fe-Cr, small-punch tests of T91; 5. Japan: Kyoto University (A. Kimura) Al-added-ODS, phase stability, He-trapping, dual beam; 6. Kazakhstan: INP (O. Maksimkin) F/M and AS, comparison with BN-350, martensite degradation; 7. Korea, Rep: KAERI (J. Kwon) MD, DD in F/M steels, with TEM, atom probe, EPA, nano-identation; 8. Netherlands: JRC-Petten (L. Debarberis) Fe-Cr ODSs (non-irradiated), EPA, SANS, TEP, TEM; 9. Poland: IAE (W. Szteke) small-punch testing of non-irradiated AS; 10. Russia: IPPE (V. Pechenkin), Kurchatov Institute (A. Ryazanov) F/M steels, neutrons, MSM, RIS; 11. Slovakia: Bratislava University (V. Slugen) ODS MA956, ODM751and Eurofer micro-comparisons; 12. Spain: Madrid University, Institute of Fusion (J. Perlado) Fe-Cr potentials, defect formation energies; 13. Switzerland: PSI (M. Pouchon) micro-pillar nano-identation, single-grain analysis and modelling; 14. Ukraine: KIPT (V. Voyevodin) super-high-dose irradiation of F/M steels, comparisons, modelling; 15. USA: LLNL (M. Fluss), LANL/UCB (P. Hosemann) ODS MA956, MA957 and K3; micro-studies; Rad. Effects Consulting (F. Garner) chief consultant of the project; NEA / OECD observer, with many participating members, discussions at WPMM. IAEA 4

5 SMoRE: do ferritic-martensitic steels NOT swell? 10 8 φ/φ (%) Best 316 Effect Ti Average 316 Ti Average 15/15Ti Best heat15/15ti Cr/Ni = 1 IAEA TM on Design, Manufacturing and Irradiation Behaviour of Fast reactors Fuels, 30 May 03 June 2011, Obninsk, Russia 6 Cr/Ni > 1 4 Phénix 2 0 Ferritic-Martensitic steels wrappers - samples dose (dpa) Ph. Dubuisson, CEA, France Voyevodin et al, KIPT, Ukraine IAEA

6 and can ODSs help? (CRP on Benchmarking of Structural Materials preselected for Advanced nuclear reactors ODS Benchmarking) Objectives 1) to review and evaluate different technologies of ODSs fabrication, 2) to define experimental techniques that are the most adequate for characterization of ODSs, 3) to create a database of qualified tests, and 3) to contribute to better understanding of ODSs operational properties and limits. 15 countries, EC and JINR: 1. Australia Australian Nuclear Science and Technology Organisation (ANSTO) 2. China CIAE & Beijing University 3. Czech Rep NRI REZ & Institute of Physics of Materials 4. EC JRC Petten 5. France CEA 6. Germany & KIT & FZR & AREVA NP 7. India IGCAR 8. Italy ENEA 9. Japan Kyoto University 10.Korea Rep KAERI 11.Netherlands NRG 12.Romania INR 13.Russia VNIINM & ITEP & JINR 14.Slovakia Bratislava University 15.Spain CIEMAT 16.Ukraine Physico-Mechanical Institute 17.USA LLNL & ORNL RCM-1 May 2011 in Vienna / IAEA (test matrix of materials and methods) IAEA RCM-2 October 2012 in Roma / ENEA (new members, joint work-plan) 6 RCM

7 IAEA CRP programme on H-induced degradation of Zr alloys DHC-1 (pressure tubes) and DHC-2 (claddings): - IAEA TECDOCs 1410 (2004) and 1649 (2010), - 15 th and 16 th International ASTM Symposia on Zr in the Nuclear Industry (2007/USA and 2010/China), - WRFP-2008 (Korea, Rep) Recommendations of IAEA Consultants Meetings (2010, 2011) and TWGFPT (2011) for a new Zr-CRP on Evaluation of Conditions for H-induced Degradation of Zr-alloys during Fuel Operation and Storage IAEA approval in June 2011, RCM-1 in October 2011 in Vienna, RCM-2 in December 2012 in Switzerland Objectives: 1. Develop and validate reproducible experimental procedures for measurement of the hydride reorientation and cracking thresholds, as well as of the brittle-to-ductile transition in of different Zr-alloys 2. Contribute to better understanding of the mechanisms of H-induced degradation in fuel operation and storage conditions by comparing results obtained from a wide array of alloys 14 members from 13 countries (10 in DHC-1 and 2) Argentina: CNEA Lithuania: LEI Brazil: IPEN Pakistan: PINSTECH Canada: AECL Romania: INR EC/Germany: ITU Russia: Bochvar Institute India: BARC Sweden: Studsvik Japan: Nippon Switzerland: PSI Korea, Rep: KAERI Kit Coleman / Canada chief consultant IAEA 7

8 TM on Design, Manufacturing and Operation Behaviour of Fuel for FR Institute of Physics and Power Engineering (IPPE) the lead of the Russian FR Programme, Obninsk (100 km from Moscow), Russia, Technical tour to the fuel production plant MSZ in Electrostal 34 participants from 10 Member States, 27 papers at 4 sessions: R&D Programmes on FR Fuel Development of SFR Oxide Fuel Development of Advanced Fuel Structural Materials Development Very impressive participation of Russian organizations: 12 papers on R&D&D, technologies, industrial practice, licencing, regulations. Round-table discussion on fast neutron irradiation testing collaboration, with the RIAR presentation (BOR-60, MBIR, SVBR, reprocessing) TM TECDOC and update to NE Series Report on structural materials for FRs (both in publication) IAEA 8

9 NEA / OECD collaborations TWGFPT NEA Databank FUMEX, IFPE Database NEA Working Party on Multi-scale Modelling January 2008 creation of the WPMM December 2008 start of SMoRE October 2012 TM on primary radiation damage (EG-PRD), dpa-crp (NA) NEA Working Party on Scientific Issues of the Fuel Cycle SMINS in cooperation with the IAEA NEA Working Party on Scientific Issues of Reactor Systems 2012 creation of the Expert Group on Reactor Fuel Performance (IFPE) TWGFPT -? IAEA 9

10 HOTLAB collaborations PIE Facilities Database Created in 1990s Electronic form in 2003 Merged with HOTLAB Database with casks information added in Modification and update in Migration into the IAEA NUCLEUS Joint PIE TM in Smolenice in 2011 Support for the HOTLAB cask development 45 facilities from 23 countries and 19 casks IAEA 10

11 IAEA-ICTP: basic radiation materials science 2008, 2009, 2010, 2011, 2012, 5-16 March 2012: Workshop on Environmental Degradation of Components in Nuclear Power Plants (with NP and NA) IAEA 11