1. SAFELIFE contribution to R&D on WWER RPV EC-JRC-Institute for Energy, Petten, The Netherlands L.Debarberis, C. Rieg 01-06-26-2-GC-BMS 1 Ukrainian-Hungarian Conference April 2006, Hungary

2. 7 Institutes in 5 Member States: JRC - Joint Research Centre IE - Petten The Netherlands - Institute for Energy IRMM - Geel Belgium - Institute for Reference Materials and Measurements ITU - Karlsruhe Germany - Institute for Transuranium elements IPSC - IHCP - IES - Ispra Italy - Institute for the Protection and the Security of the Citizen - Institute for Health and Consumer Protection - Institute for Environment and Sustainability IPTS - Seville Spain - Institute for Prospective Technological Studies

3. North-West - Holland

4. 4 Petten site

5.  > 100 LWRs in EU  ~ 100 GWe produced  Ageing of plants - Safe Operation (3S)  Needs for integrated view of PLIM  EU Enlargement  Optimisation of PLIM R&D Background 24 45 135 87 88 43 20 0 40 60 80 100 120 140 Number Of NPPs 6-1011-1515-2021-2526-30>30 Age (2000) >35 years

6. European Union new strategic goal “to become the most competitive and dynamic knowledge-based economy in the world capable of sustainable economic growth ” Towards Sustainable Nuclear Fission Energy March 2000, Lisbon European Council

7. European Platform for FISSION 01-06-26-2-GC-BMS 7 EU PLIM Activities COVERS C.A. DG RTD PERFECT I.P. PLIM NoE Proposal (NULIFE) TACIS-TAREG Joint Research Centre SAFELIFE & European Networks (AMES, etc.)

8. 01-06-26-2-GC-BMS 8 EU PLIM Activities Joint Research Centre SAFELIFE & European Networks (AMES, etc.)

9. Plant Life Management Issues RPV Lifetime assessment - embrittlement, fracture assessment - ISI, RPV cladding - VVER specific - mitigation measures, annealing - re-embrittlement SAFELIFE

10. JRC-IE Capital Facilities High Flux Reactor (HFR) 45 MW Research Reactor SAFELIFE

11. Stress-corrosion Other key Facilities Positron annihilation

12. Plant Life Management Issues key components other than RPV; including: - Primary piping, pressuriser,thermal fatigue, DMW - Internals (SCC) - SG, concrete, cables, etc. SAFELIFE

13. Effectiveness of European Networks  INTEGRATION & BARRIERS BREAKING  GLOBAL PLANNING - ‘EUROPEAN’ SCALE  SOLUTION OF GLOBAL ISSUES  TECHNOLOGY TRANSFER  STRONG CO-OPERATION WITH IAEA  REDUCTION OF DUPLICATION SAFELIFE

15. (RB NET NESC ENIQ, JRCEuropean Networks European Networks on Nuclear Safety SAFELIFE AMES AMALIA SENUF

16. NESC-IV VERSAFE ATHENA VERLIFE JRCEuropean Networks DGRTDThematic Networks (RB NET NESC ENIQ European Networks on Nuclear Safety SAFELIFE AMES AMALIA SENUF

17. NESC-IV VERSAFE ATHENA VERLIFE NESC-I PISA REFEREE MODEL ALLOYS ENUKRA NESC-II NESC-III SMILE DISWEC IRLA VOCALIST THERFAT AMESNDT AMESDosimetry MADAME RESQUE SPIQNAR BIMET VORSAC INTERWELD ADIMEWENPOWER RESTAND VAMASTWA20 COBRA REDOS GRETE FRAME IASCC&NRTDwithin PECO JRCEuropean Networks DGRTDThematic NetworksDG RTD Shared Cost &n In-kind Actions (RB NET NESC ENIQ AMES AMALIA European Networks on Nuclear Safety SAFELIFE SENUF

18. Plant Life Management Issues - Improved integrity assessment:DT/NDT & numerical modelling: - Evaluation & monitoring of degradation & stresses - Large-scale European benchmark - reliability models - Risk-based approaches - Human performance enhancement - Safety Culture SAFELIFE

19. Nuclear EU+CH PWR BWR GCR

20. COVERS Co-ordination Action “Establish a viable RTD structure with a view to enhance the scientific and technical cooperation of actors involved in VVER safety research … (utilities, manufacturers, regulatory bodies, users)”. EU operate VVER units (440 and 1000 MW) Units in operation/construction in Ukraine and Russia Operation of all units was safe and efficient National supporting technical organisations / National R&D

21. maintain and improve safety common database - “good practice” identify/initiate required R  D strengthen links - exchange of information knowledge management & dissemination platforms harmonised Safety Culture cooperation with ISTC (Ukraininan / Russian org.) COVERS Co-ordination Action General objectives of CA:

22. SOME CONTACTS / LINKS: SAFELIFE: JRC; L. Debarberis TACIS-TAREG: JRC; M. Bieth/C.Rieg PERFECT I.P.: EDF; J-P Massoud COVERS C.A.: NRI; I. Vasa NULIFE NoE:VTT, R.Rintama Nuclear Platform: CEA Direction www.jrc.nl www.jrc.nl/SAFELIFE http://projects-2006.jrc.cec.eu.int

23. 01-06-26-2-GC-BMS SAFELIFE recent results On RPV embrittlement modelling

24. 01-06-26-2-GC-BMS 24 Embrittlement Mechanistic framework MD( ,T,Ni) PRE( ,Cu,T,Ni,  rate,Mn) SEG( ,T,P,Ni,  rate ) ……….. qualitative quantitative Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE Debarberis, Sevini, Acosta, Pirfo, Bieth, Weisshaeupl, Törrönen, Kryukov & Valo International Journal Strength of Materials, ISSN 0556-171X, No. 1 (367) 2004

25. Damage = (MD, PRE, SEG, …)  MD( ,T,Ni) PRE( ,Cu,T,Ni,  rate,Mn) SEG( ,T,P,Ni,  rate ) ……….. - linear summation - quadratic option - synergisms aDBTT shift  direct matrix damage ) / (1eb Sat          precipitations )] - c0 2 (2/12/1[1 c Tanghc start   segregations n

26. Fluence, n cm -2 DBTT SHIFT, °C 0 20 40 60 80 100 120 140 160 180 200 1.00E+185.10E+191.01E+201.51E+202.01E+20 TOTAL Precipitation (Cu)) segregation (P) Direct matrix damage Semi-mechanistic analytical model for radiation embrittlement and re-embrittlement data analysis International Journal of Pressure Vessels and Piping, Volume 82, Issue 3, March 2005, 195-200 Debarberis, Kryukov, Gillemot, Acosta and Sevini

27. 0 50 100 150 200 250 0.0040.00 L Cu H Cu VH Cu Fluence, 10 18 n cm -2 DBTT SHIFT, ° C HFR data Kola data Cu up to ~ 1 wt% 80.00 model alloys – low Ni Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behavior Debarberis, Sevini, Acosta, Kryukov, Nikolaev, Amaev, Valo International Journal of Pressure Vessel and Piping; 79 (2002) 637-642

28. )](.5 [1 c2 Tangh c start   R 2 = 0.991 0 40 80 120 00.05 P, wt% Segregation parameter R 2 = 0.991 0 40 80 120 00.05 P, wt% 0 100 200 300 400 0100200300400 Kola - low Ni LYRA-HFR; low Ni Measured DBTT Shift, °C Calculated DBTT Shift, °C model alloys – low Ni HFR-LYRA + KOLA Use of the Semi-Mechanistic Analytical Model to Analyse Radiation Embrittlement of M.A.: Cu and P Effects Debarberis, Kryukov, Gillemot, Valo, Morozov, Brumovsky, Acosta, Sevini Intern. Journal of Problems of Strengths, ISSN 0556-171X, UDC 539.4, 2004, No.3.` ) / (1eb Sat   0 80 160 01.2 Cu, wt% Precipitation parameter R 2 = 1 0 80 160 01.2 Cu, wt% R 2 = 1 ] [

29. VVER 440 Evaluation of WWER – 440 radiation embrittlement data using the semi-mechanistic model Zhurko, Krasikov, Kryukov, Debarberis IAEA Specialist Meeting on Radiation Embrittlement, Gus, Russia, May 2004 0.240.055Cu 0.0450.010P Max, %Min,% - 63 points - 19 welds - high flux data - 3.5 to 60·10 19 n/cm 2 Advanced Methods for VVER RPV Embrittlement Assessment Debarberis, Kryukov, Erak, Kevorkyan and Zhurko; International Journal of Pressure Vessel and Piping, Elsevier, (2004); 81/8:695.

30. 0 20 40 60 80 100 120 140 160 180 200 5.E+191.E+202.E+203.E+204.5E+20 DBTT SHIFT, DC Re-embrittlement after annealing annealing Primary embrittlement Re-embrittlement 051015202530 0 50 100 150 Re-embrittlement of VVER-440 welds (P=~0.04 wt%) DBTT Shift, o C fluence, x10 18 cm -2, E>0.5 MeV Advanced Methods for VVER RPV Embrittlement Assessment Debarberis, Kryukov, Erak, Kevorkyan and Zhurko; International Journal of Pressure Vessel and Piping, Elsevier, (2004); 81/8:695. Fluence P=0.038 P=0.048 020406080100120140160180200 0 20 40 60 80 100 120 140 160 180 200 P=0.033 welds DBTT Calculated, ºC DBTT measured, ºC

31. VVER RPV embrittlement - effect of Nickel at 1.2 and 1.7 wt% trends from Surveillance, Tacis & other programmes data 0 20 40 60 80 100 120 140 160 0306090120150180 Fluence, 10 18 n cm -2 (E>0.5 MeV) DBTT shift, °C TAC-3 TAC-4 SS SU-1 R-3 Ni=1.7 wt% ED-3 TAC-2 SS NV-5 Z2 Ni=1.2 wt% CF=20 Ni=1.7 wt% High Nickel Low Nickel Ni=1.2 wt% Mechanistic interpretation & forecasting of radiation damage of high Ni RPV materials data Debarberis, Acosta, F.Sevini, Kryukov and Zhurko - IAEA Specialist Meeting on Radiation Embrittlement, Gus, Russia, May 2004

32. 0 100 200 300 400 0204060 fluence value, 10 18 n cm -2 (E>0.5 MeV) DBTT Shift, °C Ni=1.2 wt % Cu= 0.4 wt%, P=0.009 wt% Ni=0.004 wt % Cu= 0.41 wt%, P=0.012 wt% Ni model alloys HFR KOLA Role of nickel in a semi-mechanistic analytical model for radiation embrittlement of model alloys Journal of Nuclear Materials, Volume 336, Issues 2-3, 1 February 2005, Pages 210-216 Debarberis, Acosta, Sevini, Kryukov, Gillemot, Valo, Nikolaev, Brumovsky

33. 0 100 200 300 400 0100200300400 Kola - low Ni LYRA-HFR - low Ni high Ni (HFR+Kola) Measured DBTT Shift, °C Calculated DBTT Shift, °C aDBTT shift  = + )] (.5 [ d Tanghc start     1/2 / 1eb Sat  - - +( ) b = b 1 *Cu c = c 1 *P f(Ni) Ni inclusion in semi-mechanistic analytical model for Radiation embrittlement of model alloys and combined effects with Cu and P - Debarberis, Kryukov, Gillemot, Valo, Nikolaev, Brumovsky, Acosta & Sevini, IAEA Specialist Meeting Radiation Embrittlement, Gus, Russia, May 2004

34. 0 20 40 60 80 0102030 fluencevalue, 10 18 n cm -2 (E>0.5MeV) DBTT Shift, °C Low Ni Guide, CF=20 High Ni & Mn High Ni–LowMn Mn effect Extended analysis of VVER-1000 surveillance data International Journal of Pressure Vessels and Piping, Volume 79, Issues 8-10, August 2002, 661-664 Kryukov, Erak, Debarberis, Sevini and Acosta ”Comparison of Nickel Effects on Embrittlement Mechanisms in Prototypic WWER-1000 and A533B Steels"; R.K. Nanstad, M.A. Sokolov, M.K. Miller, and G.R. Odette - ORNL - UCSB 100 ?

35. Precipitations Fluence, n cm -2 DBTT SHIFT, °C Mn-Ni EUR 21304 EN IAEA CRP-10 in preparation (Mn-Ni) VVER-1000 Model Alloys PWR welds Mechanistic interpretation & forecasting of radiation damage of high Ni RPV materials data Debarberis, Acosta, F.Sevini, Kryukov and Zhurko - IAEA Specialist Meeting on Radiation Embrittlement, Gus, Russia, May 2004

36. 01-06-26-2-GC-BMS  ENUKRA  IRLA  ATHENA  AMES  Magnetic Methods, etc. JRC – Ukrainian Organisations Example of Co-operations

37. 01-06-26-2-GC-BMS ENUKRA Implementation of modern methods for fracture mechanics testing and transfer of western countries knowledge and experience to Ukrainian engineer relating to RPV metal condition assessment. TPC Programme

38. 01-06-26-2-GC-BMS ENUKRA project TPC Programme TECNATOM, S. A - Spain NUCLEAR RESEARCH INSTITUTE - Ukraine JRC-IE - The Netherlands NRG - The Netherlands

39. ATHENA - AMES Ukrainian organizations Institute for Problems of Strength, NAS (Kiev) Institute of Nuclear Research, NAS (Kiev) Welding Institute, NAS (Kiev) Physico-Mechanical Institute, NAS (Lviv) “Kharkov Physico-Technical Institute (Kharkov) Tractebel Suez (B) JRC IE (NL) AEA Technology (UK) AEKI (H) CEA (F) CIEMAT (S) EDF (F) FZR (G) NRG (NL) SCK.CEN (B) Tecnatom (S) Empresarios Agrupados (S) University of Cantabria (S) Framatome ANP GmbH(G) Rolls Royce (UK) British Energy (UK) BNFL Magnox Electric plc (UK) LMD Consultancy (UK) NRI Rez (CZ) VTT (FIN) IMS (BG), VUJE (SK), Skoda (CZ) Russian Research Center “Kurchatov Institute” (Moscow), CNIIKM “Prometey” (Saint Petersburg), OKB “Gidropress” (Moscow)

40. 01-06-26-2-GC-BMS TPC Programme TECNATOM, S.A – Spain JRC - The Netherlands Nuclear Research Institute – Ukraine Inst. for Problems of Strength - Ukraine NRG - The Netherlands Kurchatov Institute – Russia IRLA Transfer western countries knowledge & experience related to RPV residual life assessment, and check surveillance progs

41. IRLA Transfer western countries knowledge & experience related to RPV residual life assessment, and check surveillance progs

42. THANKS! 01-06-26-2-GC-BMS Wish you a fruitful conference, pleasant stay & social programme Ukrainian-Hungarian Conference April 2006, Hungary