Radiation stability of WWER-440 vessel materials

Amir D. Amayev, Aleksandr M. Kryukov, Vladimir I. Levit, Mikhail A. Sokolov

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

32 Scopus citations

Abstract

The main results of a complex investigation of radiation embrittlement of WWER-440 reactor vessel (RV) materials, carried out in the former USSR are presented. The object of the investigation was surveillance specimen (SS) evaluations f RV materials. It has been found that at an irradiation temperature of 270°C neither the base metal (steel 15 Kh2MFA) nor weld metal exhibits saturation of radiation embrittlement in irradiation of specimens up to neutron fluences of 7 MUL 1020 n/cm2 (E > 0.5 MeV). Regularities in the influence of impurity elements (copper and phosphorus) on radiation embrittlement of RV materials have been investigated. It is shown that radiation embrittlement of the weld metal is determined by at least four processes associated with the individual effects of copper and phosphorus, their joint effect, and the mechanism of direct buildup of radiation defects in the metal. The effect of dependence of the radiation embrittlement characteristics of the WWER-440 RV materials on the neutron flux has been found. It is shown that within the range of fluences from 1 to 5 × 1018 n/cm2 at a neutron flux of 4 MUL 1011 n/cm2·s, radiation embrittlement is stronger than in irradiation at a neutron flux of 3 to 4 × 1012 n/cm2·s. A tendency has been observed for the values of the radiation embrittlement coefficients. AF, characterizing sensitivity of the steel to radiation embrittlement, to reduce with an increase of neutron fluence in irradiation of specimens with a neutron flux of 4 × 1011 n/cm2·s.

Original languageEnglish
Title of host publicationASTM Special Technical Publication
PublisherPubl by ASTM
Pages9-29
Number of pages21
Edition1170
ISBN (Print)0803114788
StatePublished - 1993
Externally publishedYes
EventIAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels - Balatonfured, Hung
Duration: Sep 26 1990Sep 29 1990

Publication series

NameASTM Special Technical Publication
Number1170
ISSN (Print)0066-0558

Conference

ConferenceIAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
CityBalatonfured, Hung
Period09/26/9009/29/90

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