Recovery of the transition temperature of irradiated WWER-440 vessel metal by annealing

Amir D. Amayev, Alexander M. Kryukov, Mikhail A. Sokolov

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

33 Scopus citations

Abstract

The main results obtained from studying recovery of irradiation embrittlement of reactor vessel steels are presented. Investigations were carried out using WWER-440 vessel materials (base metal, weld metal). The irradiation temperature was 270°C, which corresponded to the operation temperature of the vessel wall. The effect of the annealing temperature and annealing time, neutron fluence, and phosphorus and copper impurity contents on recovery of the ductile-to-brittle transition temperature was studied. Recovery of the transition temperature depends mainly on the annealing temperature. At a phosphorus content exceeding 0.02%, recovery of properties in annealing is complicated. The effect of copper at contents lower than 0.2% has not been observed. At an annealing temperature of 420°C, residual postannealing embrittlement does not depend on neutron fluence. The results obtained in irradiation-annealing-reirradiations are also presented. After annealing, the tendency of the steel to irradiation embrittlement is not increased over that in its initial state.

Original languageEnglish
Title of host publicationASTM Special Technical Publication
PublisherPubl by ASTM
Pages369-379
Number of pages11
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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