Generate QR code
Open Access
Subscription Access
Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 1. Research program and cutting out of samples from pressure vessel internals
https://doi.org/10.22349/1994-6716-2020-103-3-135-143
Abstract
The program is presented for investigations of the metal of the most irradiated elements of the WWER-440 reactor of the Novovoronezh NPP Unit 3 decommissioned after 45 years of operation. The fragments (cylindrical samples) were cut out from various zones of the core baffle and segment of forming ring of core barrel.
Supporting agencies: This article has been written as a result of summarizing studies carried out under the project No 375123 “Investigation of the standard mechanical properties and structure integrity characteristics of the base metal and weld metal of the elements of Unit 3 of the Novovoronezh NPP to provide R&D on material science justification of operation life prolongation of equipment of WWER-440 NPP to 60 years”, funded by JSC Concern Rosenergoatom.
About the Authors
B. Z. Margolin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Dr Sc. (Eng)
49 Shpalernaya St, 191015, St Petersburg
A. Ya. Varovin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Cand Sc. (Eng)
49 Shpalernaya St, 191015, St Petersburg
A. J. Minkin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
49 Shpalernaya St, 191015, St Petersburg
Russian Federation
49 Shpalernaya St, 191015, St Petersburg
D. A. Gurin
Diakont Ltd
Russian Federation
2 Uchitelskaya St, 195274, St Petersburg
Russian Federation
2 Uchitelskaya St, 195274, St Petersburg
V. A. Glukhov
Concern Rosenergoatom
Russian Federation
6/25 Projected passage No 4062, 115432, Moscow
Russian Federation
6/25 Projected passage No 4062, 115432, Moscow
References
1. Sorokin, A.A., Margolin, B.Z., Kursevich, I.P., Minkin, A.I., Neustroev, V.S., Belozerov, S.V., Vliyanie neytronnogo oblucheniya na mekhanicheskie svoistva materialov vnutrikorpusnykh ustroistv reaktorov tipa VVER [Influence of neutron irradiation on the mechanical properties of materials for internals of VVER reactors], Voprosy Materialovedeniya, 2011, No 2 (66), pp. 131–152.
2. Margolin, B.Z., Sorokin, A.A., Shvetsova, V.A., Minkin, A.I., Potapova, V.A., Smirnov, V.I., Vliyanie radiatsionnogo raspukhaniya i osobennostei deformirovaniya na protsessy razrusheniya obluchennykh austenitnykh stalei pri staticheskom i tsiklicheskom nagruzhenii. Chast 1. Plastichnost i treshchinostoykost [The effect of radiation swelling and deformation features on the destruction processes of irradiated austenitic steels static and cyclic loading. Part 1. Plasticity and crack resistance, Voprosy Materialovedeniya, 2016, No 3 (87), pp. 159–191.
3. Margolin, B.Z., Sorokin, A.A., Shvetsova, V.A., Minkin, A.I., Potapova, V.A., Smirnov, V.I., Vliyanie radiatsionnogo raspukhaniya i osobennostei deformirovaniya na protsessy razrusheniya obluchennykh austenitnykh stalei pri staticheskom i tsiklicheskom nagruzhenii. Chast 2. Skorost rosta ustalostnykh treshchin [The effect of radiation swelling and deformation features on the destruction processes of irradiated austenitic steels static and cyclic loading. Part 2. Fatigue crack growth rate], Voprosy Materialovedeniya, 2016, No 3 (87), pp. 192–210.
4. Margolin, B.Z., Minkin, A.I., Smirnov, V.I., Fedorova, V.A., Kokhonov, V.I., Kozlov, A.V., Evseev, M.V., Kozmanov, E.A., Issledovaniye vliyaniya neitronnogo oblucheniya na staticheskuyu i tsiklicheskuyu treshchinostoikost khromonikelevoi austenitnoi stali [Research of neutron irradiation effects on static and cyclic crack resistance of nickel-chromium austenitic steel], Voprosy Materialovedeniya, 2008, No 1 (53), pp. 111–123.
5. Mansur, L.K., Lee, E.H., Maziasz, P.J., Rowcliffe, A.P., Control of helium effects in irradiated materials based on theory and experiment, J. of Nucl. Mat., 1986, V. 141–143, Part 2, pp. 633–646.
6. Garner, F.A., Radiation Damage in Austenitic Steels, Comprehensive Nuclear Materials, Konings R.J.M. (Ed.), 2012, V. 4, pp. 33–95.
7. RD-EO (Operating organization guidance document) 1.1.2.99.0944–2013: Methodology for calculating the strength and residual life of VVER-1000 internals when the service life is extended to 60 years, Moscow: Rosenergoatom, 2013.
8. Karzov, G.P., Margolin, B.Z., Mekhanizmy razrusheniya konstruktsionnykh materialov i otsenka prochnosti i rabotosposobnosti oborudovaniya AES s reaktorami razlichnogo tipa [Mechanisms of destruction of structural materials and assessment of strength and performance of NPP equipment with reactors of various types], Voprosy Materialovedeniya, 2014, No 4 (80), pp. 162–194.
9. Vasina, N.K., Margolin, B.Z., Gulenko, A.G., Kursevich, I.P., Radiatsionnoe raspukhanie austenitnykh staley: vliyanie razlichnykh faktorov. Obrabotka eksperimentalnykh dannykh i formulirovka opredelyayushchikh uravneniy [Radiation swelling of austenitic steels: the influence of various factors. Experimental data processing and formulation of constitutive equations], Voprosy Materialovedeniya, 2006, No 4 (48), pp. 69–88.
10. ASTM Е1820–17: Standard Test Method for Measurement of Fracture Toughness.
11. ASTM E647–13: Standard Test Method for Measurement of Fatigue Crack Growth Rates.
Review
For citations:
Margolin B.Z., Varovin A.Ya., Minkin A.J., Gurin D.A., Glukhov V.A. Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 1. Research program and cutting out of samples from pressure vessel internals. Voprosy Materialovedeniya. 2020;(3(103)):135-143. (In Russ.) https://doi.org/10.22349/1994-6716-2020-103-3-135-143
Views:
332
Email this article 