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SAFELIFE contribution to R&D on WWER RPV

01-06-26-2-GC-BMS. SAFELIFE contribution to R&D on WWER RPV. L.Debarberis, C. Rieg. Ukrainian-Hungarian Conference April 2006, Hungary. EC-JRC-Institute for Energy, Petten, The Netherlands. 1. JRC - Joint Research Centre. 7 Institutes in 5 Member States:. IE - Petten The Netherlands

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SAFELIFE contribution to R&D on WWER RPV

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

  2. JRC - Joint Research Centre 7 Institutes in 5 Member States: 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 - IspraItaly - Institute for the Protection and the Security of the Citizen - Institute for Health and Consumer Protection - Institute for Environment and Sustainability IPTS -SevilleSpain - Institute for Prospective Technological Studies

  3. North-West - Holland

  4. Petten site 4

  5. 140 135 120 Number Of NPPs 100 88 87 80 60 45 43 40 24 20 20 0 6-10 11-15 15-20 21-25 26-30 >30 >35 years Age (2000) Background • > 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

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

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

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

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

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

  11. Positron annihilation Other key Facilities Stress-corrosion

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

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

  14. NET NESC ENIQ ( , RB SAFELIFE European Networkson Nuclear Safety JRC European Networks AMES AMALIA SENUF SAFELIFE

  15. NET NESC ENIQ ( RB SAFELIFE European Networkson Nuclear Safety JRC European Networks VERLIFE AMES AMALIA NESC - IV SENUF VERSAFE ATHENA DG RTD Thematic Networks SAFELIFE

  16. ( RB SAFELIFE European Networkson Nuclear Safety JRC European Networks REFEREE BIMET ADIMEW ENPOWER PISA NESC - I FRAME VORSAC GRETE RESQUE REDOS VERLIFE IRLA NET COBRA AMES AMALIA INTERWELD NESC NESC - IV AMES NDT RESTAND NESC - III SENUF ENIQ THERFAT DISWEC VERSAFE VOCALIST ATHENA MODEL ALLOYS AMES Dosimetry SPIQNAR VAMAS TWA20 MADAME SMILE NESC - II ENUKRA IASCC & NRTD within PECO DG RTD Shared Cost &n DG RTD Thematic Networks SAFELIFE In-kind Actions

  17. SAFELIFE 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

  18. Nuclear EU+CH PWR BWR GCR

  19. 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

  20. COVERS Co-ordination Action General objectives of CA: • 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.)

  21. 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

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

  23. qualitative quantitative 01-06-26-2-GC-BMS Embrittlement Mechanistic framework MD(F,T,Ni) PRE(F,Cu,T,Ni, Frate,Mn) SEG(F,T,P,Ni, Frate) ……….. 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 24

  24. precipitations - F F é ù / + * - + Sat b 1 e ( ) ê ú ë û F - F start + * + * c 1 [ 1 / 2 1 / 2 Tangh ( )] - c0 c 2 segregations MD(F,T,Ni) PRE(F,Cu,T,Ni, Frate,Mn) SEG(F,T,P,Ni, Frate) ……….. • linear summation • quadratic option • synergisms  Damage = (MD, PRE, SEG, …) direct matrix damage n = * F DBTT a shift

  25. TOTAL Precipitation (Cu)) segregation (P) Direct matrix damage 200 180 160 140 120 100 DBTT SHIFT, °C 80 60 40 20 0 1.00E+18 5.10E+19 1.01E+20 1.51E+20 2.01E+20 Fluence, n cm-2 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

  26. P up to ~ 0.04 wt% HFR data Kola data VH Cu & H P 300 VH Cu & M P 250 C ° 200 H Cu & H P 150 DBTT SHIFT, 100 L Cu & H P 50 0 0.00 40.00 80.00 Fluence, 10 n cm 18 - 2 model alloys – low Ni Cu up to ~ 1 wt% 250 HFR data Kola data VH Cu 200 C ° 150 DBTT SHIFT, H Cu 100 50 L Cu 0 80.00 0.00 40.00 Fluence, 10 n cm 18 - 2 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

  27. 120 120 2 2 R R = 0.991 = 0.991 2 2 R R = 1 = 1 160 160 80 80 Segregation parameter Precipitation parameter 80 80 40 40 0 0 0 0 0 0 0.05 0.05 0 1.2 0 1.2 P, wt% P, wt% Cu, wt% Cu, wt% F - F - F F / * - [ ] c b 1 e ( ) * + * 1 [ .5 .5 ( )] Tangh start Sat c2 model alloys – low Ni HFR-LYRA + KOLA 400 300 Measured DBTT Shift , °C 200 100 Kola - low Ni LYRA-HFR; low Ni 0 0 100 200 300 400 Calculated DBTT Shift , °C 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.`

  28. 240 All welds 210 63 points , C o 180 k T 150 D 120 Min,% Max, % Measured 90 P 0.010 0.045 60 Cu 0.055 0.24 30 0 0 30 60 90 120 150 180 210 240 o D T , C Calculated k VVER 440 • 63 points • 19 welds • high flux data • - 3.5 to 60·1019 n/cm2 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 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.

  29. 200 180 160 P=0.038 P=0.048 140 DBTT measured, ºC 120 100 welds 80 P=0.033 60 40 20 0 0 20 40 60 80 100 120 140 160 180 200 DBTT Calculated, ºC Re-embrittlement Re-embrittlement of VVER-440 welds 150 200 (P=~0.04 wt%) 180 Primary embrittlement C o 160 Re- embrittlement after annealing 140 100 120 DBTT SHIFT, DC DBTT Shift, 100 annealing 80 60 50 40 20 0 5.E+19 1.E+20 2.E+20 3.E+20 4.5E+20 0 0 5 10 15 20 25 30 Fluence 18 -2 fluence, x10 cm , 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.

  30. VVER RPV embrittlement - effect of Nickel at 1.2 and 1.7 wt% trends from Surveillance, Tacis & other programmes data 160 High Nickel TAC-3 140 TAC-4 120 SS SU-1 R-3 100 Ni=1.7 wt% Ni=1.7 wt% 80 ED-3 DBTT shift, °C Ni=1.2 wt% TAC-2 60 SS NV-5 Z2 40 Low Nickel Ni=1.2 wt% 20 CF=20 0 0 30 60 90 120 150 180 18 -2 Fluence, 10 n cm (E>0.5 MeV) 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

  31. model alloys HFR KOLA 400 Ni=1.2 wt % Cu= 0.4 wt%, P=0.009 wt% 300 Ni 200 DBTT Shift , °C 100 Ni=0.004 wt % Cu= 0.41 wt%, P=0.012 wt% 0 0 20 40 60 fluence value, 1018 n cm-2 (E>0.5 MeV) 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

  32. f(Ni) high Ni (HFR+Kola) F F F - F - / start Sat - + [ ( + b ( 1 e ) c + Tangh )] .5 .5 d 1/2 = F DBTT a shift b = b1*Cu c = c1*P 400 300 200 Measured DBTT Shift , °C 100 Kola - low Ni LYRA-HFR - low Ni 0 0 100 200 300 400 Calculated DBTT Shift , °C 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

  33. High Ni – Low Mn Mn effect 100 ? 80 60 , °C Shift 40 DBTT High Ni & Mn 20 Low Ni ”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 Guide, CF=20 0 0 10 20 30 18 - 2 fluence value, 10 n cm (E>0.5 MeV ) 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

  34. DBTT SHIFT, °C Fluence, n cm-2 Precipitations Mn-Ni VVER-1000 Model Alloys PWR welds EUR 21304 EN 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 IAEA CRP-10 in preparation (Mn-Ni)

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

  36. TPC Programme 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. 01-06-26-2-GC-BMS

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

  38. ATHENA - AMES 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) • 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)

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

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

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

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