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

Author:

Margolin B. Z.1,Varovin A. Ya.1,Minkin A. J.1,Gurin D. A.2,Glukhov V. A.3

Affiliation:

1. NRC “Kurchatov Institute” – CRISM “Prometey”

2. Diakont Ltd

3. Concern Rosenergoatom

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.

Publisher

FSUE CRISM Prometey

Reference11 articles.

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.

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