Surveillance Specimen Programs of WWER RPV Steels

Surveillance Specimen Programs of WWER RPV Steels
WWER RPV EMBRITTLEMENT

WWER RPV EMBRITTLEMENT
Surveillance Introduction to WWER RPV Embrittlement WWER RPV EMBRITTLEMENT

Surveillance SOA Report N. ALEKSENKO, 1981 WWER RPV EMBRITTLEMENT

Surveillance What is SURVEILLANCE? WWER RPV EMBRITTLEMENT

Surveillance Surveillance Capsule WWER RPV EMBRITTLEMENT

Surveillance In the SSSP were for the analyses of WWER-440 steels mechanical properties used three type of specimen: tensile samples Gagarinsky type, Charpy-V samples, COD samples. WWER RPV EMBRITTLEMENT

Surveillance WWER RPV EMBRITTLEMENT Irradiation capsule Charpy type from Standard Surveillance Program WWER-440

Surveillance Trend curve of Tkf for the weld No.4 results are from SSSP Jaslovské Bohunice unit 3

Reconstituted Charpy specimen by electron beam welding method
Surveillance Reconstituted Charpy specimen by electron beam welding method

Surveillance

Surveillance: Critical Questions (1) WWER RPV EMBRITTLEMENT
Comparison of surveillance specimen results from WWER-440 and 1000 units Surveillance specimen programs modernization The analyses of irradiated samples from RPV materials by modern methods application The irradiation embrittlement of the RPV`s weld metal due to the effects of impurities WWER RPV EMBRITTLEMENT

Surveillance: Critical Questions (2)
The evaluation of RPV`s irradiation embrittlement trends during planned LTO Critical analyses of existing rules and codes, used by lifetime evaluation Theoretical models which may more or less describe the influence of impurities in RPV steels WWER RPV EMBRITTLEMENT

Surveillance: Consolidated Conclusions (1)
Current SSP are more precise, giving the more reliable results for operators and national authorities, but still we need permanent effort to enable implementation of new progressive methods for the results evaluation of irradiated samples testing. The new SSP must be based on philosophy to support reliable operation of individual units during standard and emergency operation too. WWER RPV EMBRITTLEMENT

Surveillance: Consolidated Conclusions (2)
The future SSP must be created so, that they enable to monitor the influence of new generation of fuel on the irradiation embrittlement and power uprate. New SSP must support the long term operation of older units as minimum for 20 years after originally planned operational time. WWER RPV EMBRITTLEMENT

Surveillance: Open Issues (1)
Against the fact, that great effort was put into surveillance programs improvement several issues are still not clarified: how to estimate the plants operation extension above the original lifetime if there is a great lack of experimental materials, the procedures for evaluation of power uprate influence, WWER RPV EMBRITTLEMENT

Surveillance: Open Issues (2)
what are the properties of high irradiated heat affected zone around the RPV’s welds and below the austenitic cladding, the procedures for evaluation of new fuel generation influence, how to test the irradiation embrittlement of operated reactor internals. WWER RPV EMBRITTLEMENT

Surveillance: Reviewed Papers
Base publications, books and standards (1) [1] Guide for strength analysis of the equipment and pipelines of nuclear power units PNAE G , M. Energoatomizdat, 1989. [2] Technique of transition temperature evaluation for reactor pressure vessel metal during operation and after annealing. ICP MAE, МКТ-02-98, 1998. [3] Technique of strength parameters prediction for reactor pressure vessel material under reirradiation. " Rosenergoatom ", RD EO , 2000. [4] Technique of transition temperature evaluation of reactor pressure vessels using results of sub size specimens’ tests. IAE, inv. N 60/854, 1992. [5] Technique of specimen’s reconstitution for impact and three-point bend tests of VVER reactor pressure vessel materials. "Rosenergoatom ", RD EO , 2000. [6] Standard Guide for Prediction Neutron Radiation Damage to Reactor Vessel Materials, E706 IIF, ASTM E 900–98. WWER RPV EMBRITTLEMENT

Base publications, books and standards (2)
[7] Alekseenko, N. N., Amaev, A. D., Gorynin, I. V., Nikolaev, V. A., “Radiation Damage of Pressure Vessel Steels of Water-cooled Reactors,” Moscow, Energoatomizdat, 1981. [8] ASTM E “Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range”, Annual Book of ASTM Standards, vol.03.01, pp [9] ASTM Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF), ASTM E-185 [10] US CFR, Nuclear Regulatory Commission, Part 50 (10CFR50) – Domestic Licensing of Production and Utilization Facilities, Appendix H – Reactor Vessel Material Surveillance Program Requirements. [11] KTA Monitoring of Radiation Damage in LWR Reactor Pressure Vessels, Safe Technical Rule of KTA.

Base publications, books and standards (3)
[12] Guidelines for prediction of irradiation embrittlement of operating WWER-440 reactor pressure vessel, IAEA-TECDOC- 1442, IAEA, Vienna, 2005. [13] L.M. Davies: „A comparison of western and eastern nuclear reactor pressure vessel steels“, AMES Report No. 10, EUR 17327, EC, Luxembourg, 1997. [14] R. Gerard: „ Survey of national regulatory requirements“, AMES Report No. 4, EUR 16305, EC, Luxembourg, 1995. [15] Shtrombakh, Ya.I.: “Experimental validation of radiation safety life for VVER- 440RPV material,” Doctor of sciences thesis, Moscow, RRC “Кurchatov Institute”,1998. [16] Nikolaev, Yu.A.:“Radiation embrittlement of VVER reactor pressure vessel steels,” Doctor of sciences thesis, Moscow, RRC “Кurchatov Institute”, 2003.

International projects dealing with Surveillance Programs (1)
[1] COBRA. VVER 440/213 Surveillance Specimens Temperature Measurement. PH/2.01/95. [2] Integrity Assessment of VVER 440/213 RPV’s, Implementation of Dynamic Fracture Mechanics Properties and Criteria (VVER- 440). [3] PISA. Phosphorus Role on Embrittlement Effects and Development of a Physically Based Model. [4] TACIS R 1.1/91. Reactor Vessel Embrittlement (VVER 440). [5] TACIS R 2.06/96. Surveillance Program for VVER 1000 RPV (VVER 1000). [6] TACIS SRR 2/95. Development of Advanced Method for the Evaluation of Irradiation Embrittlement of VVER 1000/320 Type RPV`s (VVER 1000). [7] TACIS R 1.1/91 „Reactor vessel embrittlement (VVER 440)“. [8] TACIS U 1.02/92 A2 Evaluation of reactor pressure vessel integrity of South Ukraine 1–3 including embrittlement aspects (VVER 1000)

[9] TACIS R 2.09/94 Integrity assessment of VVER 1000 RPV’s including embrittlement aspects. [10] TACIS R 2.02/95 Reactor pressure vessel integrity assessment (VVER 440). [11] TACIS SRR 2/95 Development of advanced method for the evaluation of irradiation embrittlement of VVER 1000/320 type RPV’s. [12] TACIS R 6.01/96 Ageing of RPV. Embrittlement analyses at the VVER Greifswald RPV’s (VVER 440). [13] TACIS R/TSO/VVER01C Licensing related assessment for design and operational safety of VVER-Subtask C reactor embrittlement. [14] PH/91 RPV Embrittlement units 1–4 and RPV sampling on unit 2 (Kozloduy).

[15] PH/92 Kozloduy unit 1 RPV assessment, PTS and spectroscopy analyses. [16] PH/93 Kozloduy RPV 1 Assessment: testing. [17] PH/2.01/95 Integrity assessment of VVER 440/213 RPV’s, implementation of dynamic fracture mechanics properties and criteria (VVER 440). [18] FRAME Validation of fracture toughness trend curve for RPV materials. [19] GRETE Round robin exercise on non-destructive techniques to assess and/or monitor materials properties degradations. [20] MODEL ALLOYS Phosphorus, copper, nickel effects on embrittlement. [21] L. M. Davies, F. Gillemot, L. Yanko, V. Lyssakov: „The IRPVM-DB Database“

[22] F. Gillemot, L M Davies: „Examples of the use of the IRPVM-DB Database“ [23] J. Strosnider et al: RPV Status Report, USNRC Report NUREG 1511, Dec 1994 [24] R. Gerard: AMES 4 (95) EUR 16305, En. „Survey of national regulatory requirements“ JRC-IAM of EC, PB 2.NL-1755 ZG Petten, The Netherlands. [25] P. Petrequin: AMES 6 (96) EUR 16455, En, „A review of formulas for predicting irradiation embrittlement of reactor vessel materials“, JRC-IAM of EC, PB2.NL-1755 ZG Petten, The Netherlands. [26] L. M. Davies: AMES 10(97) EUR 17327, En, „A comparison of Eastern and Western RPV Steels“,

Publications from International journals (1)
[1] Miller, M.K., Jayaram, R., Russell, K.F.: Characterization of phosphorus segregation in neutron-irradiated Russian pressure vessel steel weld. J. Nucl. Mater. 225, 215±224. [2]Miller, M.K., Russell, K.F., APFIM characterization of a high phosphorus Russian RPV weld. Appl. Surf. Sci. 94/95, 278±383. [3]Gurovich, B.A., Kuleshova, E.A., Nikolaev, Yu.A., Shtrombach, Ya.I.: Assessment of relative contributions from different mechanisms to radiation embrittlement of reactor pressure vessel steels. J. Nucl. Mat. 246, 91–120. [4] Korolev, Yu.N., Kryukov, A.M., Nikolaev, Yu.A., Platonov, P.A., Shtrombakh, Ya.I., Langer, R., Leitz, C., Rieg, C.-Y.: Assessment of Irradiation response of WWER-440 welds using samples taken from Novo-Voronezh Unit 3 and 4 reactor pressure vessels. Nucl. Eng. Des.185, 309–317. [5] Kryukov, A., Platonov, P., Shtrombakh, Y., Nikolaev, V., Klausnitzer, E., Leitz, C., Rieg, C.: Investigations of samples taken from Kozloduy Unit 2 reactor pressure vessel. Nucl. Eng. Des. 160, 59– [6] Nikolaev, Y.A., Nikolaeva, A.V., and Shtrombakh, Y.I.: “Radiation embrittlement of low alloy steels,” Intern. J. Pressure Vessel Piping, 2002, v. 79, N 8−10, pp. 619−636. [7] Nikolaeva, A.V., Nikolaev, Yu.A., and Kevorkyan, Yu.R.: “Experimental – statistic analysis of radiation embrittlement of VVER-440 reactor pressure vessel steels,” Atomnaya Energiya, 2001, v. 90, No. 4, pp. 260−267.

[8] Nikolaev, Yu.A., Nikolaeva, A.V., Kryukov, A.M., Levit, V.I., and Korolev, Yu.N.: “Radiation embrittlement and thermal annealing behavior of Cr–Ni–Mo reactor pressure vessel materials,” J. Nucl. Mater., 1995, v. 226, pp. 144–155. [9] Nikolaeva, A.V., Nikolaev, Yu.A., and Kevorkyan, Yu.R.: “Mechanical properties recovery of irradiated steels under thermal annealing,” Atomnaya Energiya, 2001, v. 90, No. 6, pp. 457−460. [10] Kryukov, A., Platonov, P., and Shtrombakh, Ya., : “Investigation of samples taken from Kozloduy unit 2 reactor pressure vessel,” Nucl. Engng. Des., 1996, v. 160, pp. 59−76. [11] Platonov, P.A., Nikolaev, Y.A., and Shtrombakh, Y.I.: “Radiation embrittlement kinetics of the first generation of VVER-440 RPV’s after post-irradiation annealing,” Intern. J.Pressure Vessel Piping, 2002, v. 79, N 8-10, pp. 643−648. [12] Nikolaenko, V.A., Krasikov, Ye.A, Nikolaev, Yu.A., Korolyov, Yu.N., and Boksha, N.S.: “The neutron flux effect on radiation embrittlement of VVER-440/213 reactor pressure vessel steels,” Atomnaya Energiya, 2004, v. 97, No. 3, pp. 177−182. [13] Pareige, P., Stoller, R.E., Russel, K.F., and Miller, M.K.: “Atom probe characterization of the microstructure of nuclear pressure vessel surveillance materials after neutron irradiation and after annealing treatments,” J. Nucl. Mater., 1997, v. 249, pp

[14] Kuleshova, Е.А, Gurovich, B.А., Shtrombakh, Y.I, Nikolaev, Yu.А.,Pechenkin,V.А.: “Microstructural behavior of VVER-440 reactor pressure vessel steels under irradiation to neutron fluences beyond the design operation period,” J. Nucl. Mater., 2005, v. 342, pp. 77–89. [15] Zabusov, O., Krasikov, E., Kozodaev, M., Suvorov, A., Pareige, P, Radiguet, R.: “Redistribution of impurity and alloying elements in VVER-440 reactor pressure vessel steel under action of operational factors,” Questions of a nuclear science and techniques. A series: Physics of radiating damages and radiation material science. 2003, No. 3, pp [16] Nikolajev T.J.Williams, D.Ellis, C.A.English, J.Hyde A.: The model of irradiation damage in high nickel submerged arc welds. International Journal of Pressure Vessels and Piping, 2002, v. 79, pp [17] Nikolaev, Y. A., Nikolaeva, A. V., and Shtrombakh, Y. I.: “Radiation Embrittlement of Low-alloy Steels,” Int. J. Pressure Vessels Piping, Vol. 79, No. 8–10, 2002, pp. 619–636. [18] Shtrombakh, Ya. I., Nikolaev, Yu. A., and Platonov, P. A.: “The Radiation Design Operation Period of Reactor Pressure Vessel Steels for Operating VVER Units,” At. Energ., Vol. 98, No. 6, 2005. [19] Nikolaev, Yu. A., Nikolaeva, A. V., Kryukov, A. M., Levit, V. I., and Korolev, Yu. N.: “Radiation Embrittlement and Thermal Annealing Behavior of Cr–Ni–Mo Reactor Pressure Vessel Materials,” J. Nucl. Mater., Vol. 226, 1995, pp. 144–155. [20] Nikolaeva, A. V., and Nikolaev, Yu. A.: “Mechanism of the Drop in the Dependence of Yield Stress on Neutron Irradiation Dose for Low-Alloy Steel,” Mater. Sci. Eng., A, Vol. A234–236, 1997, pp. 915–917.

[21] Williams, T. J., Ellis, D., English, C. A., and Hyde, J., “A Model of Irradiation Damage in High Nickel Submerged Arc Welds,” Int. J. Pressure Vessels Piping, Vol. 79, 2002, pp. 649–660. [22] Nikolaeva, A. V., Nikolaev, Yu. A., and Kevorkyan, Yu. R., “Radiation Embrittlement of VVER-1000 RPV Steels,” At. Energy, Vol. 90, No. 5, 2001, pp. 359–366. [23] Wallin, K., The size effect in KIC results. Eng. Fract. Mech., 1985, 22, [24] Wallin, K. The scatter in KIc results, Eng. Fract. Mech, 1984, 19, [25] Margolin B.Z., Karzov G.P., Shvetsova V.A., Kostylev V.I.: Modelling for transcrystalline and intercrystalline fracture by void nucleation and growth. Fatigue Fract. Eng. Mater. Struct., 1998,n°21, pp [26] Margolin B.Z., Gulenko A.G., Shvetsova V.A: Improved probabilistic model for fracture toughness prediction for nuclear pressure vessel steels, Int. J. Pres. Ves. Piping 1998, n°75, pp [27] Margolin B.Z., Shvetsova V.A, Gulenko A.G., Ilyin A.V., Nikolaev V.A., Smirnov V.I.: Fracture toughness predictions for a reactor pressure vessel steels in the initial and highly embrittled states with the Master Curve approach and a probabilistic model, Int. J. Pres. Ves. Piping 2002, n°79, pp [28] Margolin B.Z., Kostylev V.I.: Radiation embrittlement modeling for RPV steels: II. Ductile fracture toughness prediction , Int. J. Pres. Ves. Piping 1999, n°76, pp

[29] Margolin B.Z., Kostylev V.I., Ilyin A.V. and Minkin A.I.: Simulation of JR-curves for reactor pressure vessel steels on the basis of a ductile fracture model, Int. J. Pres. Ves. Piping 2001, n°78, pp [30] A. Ballesteros, J. Bros, L. Debarberis, F. Sevini, D. Erak, S. Gezashchenko, A. Kryukov, Y. Shtrombakh, G. Goloschapov: Nucl. Eng. Des. 235 (2005) 411. [31] L. Debarberis, F. Sevini, B. Acosta, A. Kryukov, Y. Nikolaev, A.D. Amaev, M. Valo: Int. J. Pres. Ves. Pip. 79 (2002) 637. [32] L. Debarberis, B. Acosta, F. Sevini, A. Kryukov, F.Gillemot, M. Valo, A. Nikolaev, M. Brumovsky: J. Nucl. Mater. 336 (2005) 210. [33] A. Ballesteros: Conversion table of material damage indexation for all different European reactor types. AMES Rep. 13, EUR 18693b, European Commission, Luxembourg, 1999. [34] L. Debarberis, B. Acosta, A. Zeman, F. Sevini, A. Ballesteros, A. Kryukov, F. Gillemot, M. Brumovsky: Scr. Mater.53 (2005) 769. [35] Kupca, L. et al.: Monitoring of the condition of important components of a VVER-440 primary circuit Safety of Nuclear Energy, (May-Jun 2007) v. 15(5-6) p ISSN [36] Kupca, L.; Vaclavkova, J.; Balak, J.: Irradiation degradation monitoring of reactor pressure vessels material for WWER 440 type reactor Spravodajca - VUJE SSN X; CODEN SVELEU, Journal Article

[37] Kupca, L.; Beno, P.: Irradiation embrittlement monitoring of WWER-440/213 type RPV`s Nuclear Engineering and Design, 5. ASME/SFEN/JSME international conference on nuclear engineering: Nuclear advances through global cooperation (ICONE-5) Nice (France) May 1997 [38] Kupca, L.; Cepcek, S.: Thermal annealing of the reactor pressure vessel NPP Unit 2 in Jaslovske Bohunice for its radiation embrittlement regeneration Steele, L.E. (ed.). Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume). Philadelphia, PA (United States). ASTM p. p ISBN [39] Kupca, L.; Beno, P.: Analysis of the results from the surveillance specimen program for reactor pressure vessels of nuclear power plant V-2 Jaslovske Bohunice Ibidem p. p [40] Repka, M.; Kupca, L.: Thermally annealing the reactor pressure vessels at Bohunice V1 ISSN ; Nuclear Engineering International (Dec 1993). v. 38(473). p. 26, 28

Publications from International Conferences (1)
1. Fekete, T.; Gillemot, F.; Tatfir, L.: "Investigation of the Cladding Effect Using Elasticplastic FE Simulation of PTS Phenomena" IAEA Specialist Meeting "Methodology for Pressurized Thermal Shock Evaluation" IWG-LNPP-00/1 pp Rockville, Maryland USA July. 2000 2. Gillemot, F., Uri, G, Fekete, T.: Special Features of WWETR-440 Reactors at PTS Analysis". IAEA Specialist Meeting "Methodology for Pressurized Thermal Shock Evaluation" IWG-LMNPP-00/1 pp Rockville, Maryland USA July. 2000 3. Oszwald, F.: ,,Preliminary Evaluation of the Results from the Surveillance Specimens for RPV of Paks NPP according to Proposal Master Curve". IAEA Specialist's Meeting on "Irradiation Embrittlement and Mitigation", Madrid April. 1999 4. Gillemot, P. Trampus, and J. Rittinger: Evaluation of WWER-440 Surveillance at Paks NPP’s "Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels”, ASTM STP 1011, L. E. Steele, Ed., Philadelphia 1988 pp.73-82 5. Gillemot, I. Havas, J. Rittinger, A. Fehervary: Experiences in comparison of large and small fracture mechanical specimens. IAEA Specialist's meeting on Large Scale Testing. MPA Stuttgart I988 May Fracture Mechanics Verification by Large-scale testing. EGF/ESIS Pub. 8. Ed. by K. Kussmaul. p.32. 6. Gillemot; P. Trampus: “Main Features of the Pressurized Component Life Time Management Related R&D Activity in Hungary” TC Meeting of the IWG on LM of Nuclear Power Plants. Vienna February 1992.

7. Gillemot: “Survey of Irradiation Embrittlement Effects of the Mechanical Properties of Alloyed Steels”. Materials Science Forum Vol (1992) p. 527 8.Trampus, F. Gillemot: Paks Reactor Pressure Vessels Meet the Requirements Science and Technology in Hungary. 1992 August, Budapest 9.Gillemot, F.; Trampus, P.; Oszwald, F.; Uri, G.: Surveillance Extension Experience at WWER-440 type Reactors. Presented on the IAEA/NEA Specialist's meeting on "Irradiation Embrittlement and Optimization of Annealing" Paris, September 20-24, 1993. 10.Gillemot F.; Fekete T.; Oszwald F.; Material Reference Curve Selection, in IAEA IWG-LMNPP 94/4. Proc. of Specialist's Meeting held in San Carlos de Bariloche, Argentina, March 1994 11.Oszwald, F. Gillemot, L. Tóth: Preliminary results of the surveillance extension program of NPP Paks. IAEA Specialist Meeting, "Irradiation embrittlement and mitigation" Espoo, Finland, Oct. 1995 12. Davies, L. M.; Gillemot, F.; Lyssakov, V.: "PTS and the database." IAEA Specialist's Meeting on Pressurised Thermal Shock Esztergom, Hungary, 6-8 May 13.Davies, L. M.; Gillemot, F.; Yanko, L; Lyssakov V.: "The IRPVM Database" IAEA Specialist's Meeting on PTS Esztergom, Hungary, 5-8 May 14.Elter, J.; Fekete, T.; Gillemot, F.; Oszwald, F.; Mar6thy, L; Ratkay, S.: "PTS assessment - the basis of life time evaluation at NPP Paks." IAEA Specialist's Meeting on Pressurised Thermal Shock Esztergom, Hungary, 5-8 May

15. Gillemot, F.; Oszwald F.; Gillemot L.; Uri G.; Pirfo S.: "Synergetic effects of irradiation and thermal embrittlement" IAEA Specialist's Meeting on Irradiation Effects and Mitigation Vladimir, Russia, Sept. 1997 16. Korolev, Yu. N., Shtrombakh, Ya. I., and Nikolaev, Yu. A., et al.: “Application of the Reconstituted Subsize Specimens for Assessment of Irradiation Embrittlement of RPV Steels,” Small Specimen Test Techniques, ASTM STP 1418, ASTM International, West Conshohocken, PA, 2002, pp. 151–178. 17. Amaev, A. D., Kryukov, A. M., and Sokolov, M. A.: “Recovery of Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing,” Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels, ASTM STP 1170, ASTM International, West Conshohocken, PA, 1993, pp. 369–379. 18. Zaritsky, S.M., Platonov, P.A., and Nikolaev, Yu.A., e.a.: “Review of problems and requirements in VVER reactor-type pressure vessel dosimetry,” Reactor Dosimetry:Radiation Metrology and Assessment, ASTM STP 1398, 2001, pp. 53–60. 19. Brodkin E.D., Egorov A.L., Vikhrov V.I., Zaritsky S.M.: “The determination of the VVER-1000 surveillance neutron fluence using the 54Mn activity measurements and tort neutron spectra calculations”. Proceedings of the 1996 Topical Meeting Radiation protection and shielding. North Falmouth, MA, April 1996, vol. 1. Published by AN Society, La Grande Park, IL 60526, USA. 20. Kupca, L.: Current status of Irradiation Embrittlement Monitoring Programs of RPV`s in the Slovak Republic NPP`s Proceedings of 14-th International Conference IGRDM Pittsburgh – USA, April 2008

21. Kupca, L.: Aging Management of Safety Related Components of VVER-440 Units operated in Slovak Republic Proceedings from 5-th International Scientific and Technical conference „Safety Assurance of NPP with WWER, 29-th May - 1-st June 2007 Podolsk, Russia 22. Brumovsky, M., Kupca, L.: Prediction of irradiation embrittlement in WWER-440 reactor pressure vessel materials 13. International conference on nuclear engineering Beijing (China) May 2005 Atomic Energy Press p. p. 51,ISBN 23. Kupca, L: Irradiation embrittlement monitoring programmes in the Slovak Republic Nuclear Power Plants International symposium Fontevraud 5- Royal Abbey (France) Sep 2002 24. Kupca, L.; Stanc, S.; Simor, S.: Irradiation temperature measurement of the reactor pressure vessel surveillance specimen in the programmes of radiation degradation monitoring Inter. symposium on safety related measurements in PWR`s, Smolenice, (Slovakia) Sep 2001 25. Kupca, L.: Preliminary results of scoop samples analysis from RPV’s of Bohunice V-1 NPP IAEA specialists meeting on irradiation effects and mitigation Vladimir (RF) Sep 1997 26. Kupca, L.: The bulk sampling of the RPV’s NPP V-1 Jaslovske Bohunice Specialists meeting on irradiation embrittlement and mitigation. Espoo (Finland) Oct 1995 27. Kupca, L.et al.: Chemical composition determination and hardness measurements of Bohunice 1 and 2 RPV’s of RPV’s Inter. workshop on WWER-440 reactor pressure vessel embrittlement and annealing. Zavazna Poruba (Slovakia), March 1994

28. Kupca, L.; Cepcek, S.: Thermal annealing of the reactor pressure vessel NPP Unit 2 in Jaslovske Bohunice for its radiation embrittlement regeneration Steele, L.E. (ed.). Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume). Philadelphia, PA (United States). ASTM p. p ISBN 29.Kupca, L., et al.: The results of the surveillance specimen program performed in the RPV’s NPP V-2 in Jaslovske Bohunice Specialists meeting on irradiation embrittlement and optimization of annealing. Paris (France) Sep 1993 30. Kupca, L.; Brezina, M.; Beno, P.: The preliminary results of the thermal annealing processes performed on the RPV’s NPP V-1 in Jaslovske Bohunice 31. Kupca, L.; Beno, P.: Analysis of the results from the surveillance specimen program for reactor pressure vessels of nuclear power plant V-2 Jaslovske Bohunice Steele, L.E. (ed.). Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume). Philadelphia, PA, American Society for Testing and Materials p. p

Surveillance: Lessons Learnt
To analyze and find the answers for open issues presented above is great challenge for: the future irradiation embrittlement research projects, the new surveillance programs planned for older, but for the new generation of NPP's too, till this time are implemented individual approach for the irradiated specimen testing even for the same type of reactors. WWER RPV EMBRITTLEMENT

Surveillance Specimen Programs of WWER RPV Steels

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