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Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms Other than Radiation Hardening

Gurovich, BA
Head of Lab., Head of Mechanical Test Group, Leading Research Scientist, Leading Research Scientist, Deputy Director,Reactor Materials Division Russian Research Center “Kurchatov Institute”,

Korolev, YN
Head of Lab., Head of Mechanical Test Group, Leading Research Scientist, Leading Research Scientist, Deputy Director,Reactor Materials Division Russian Research Center “Kurchatov Institute”,

Kuleshova, EA
Head of Lab., Head of Mechanical Test Group, Leading Research Scientist, Leading Research Scientist, Deputy Director,Reactor Materials Division Russian Research Center “Kurchatov Institute”,

Nikolaev, YA
Head of Lab., Head of Mechanical Test Group, Leading Research Scientist, Leading Research Scientist, Deputy Director,Reactor Materials Division Russian Research Center “Kurchatov Institute”,

Shtrombakh, YI
Head of Lab., Head of Mechanical Test Group, Leading Research Scientist, Leading Research Scientist, Deputy Director,Reactor Materials Division Russian Research Center “Kurchatov Institute”,

Pages: 25    Published: Jan 1999

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Source: STP1325-EB

Abstract

Data on Russian pressure vessel steels in unirradiated, irradiated and annealed conditions are presented. The experimental methods applied included impact testing, fractography, electron microscopy and Auger spectroscopy. Contributions from different mechanisms to radiation embrittlement were evaluated. These studies enabled us to conclude that the major contribution to radiation induced ductile-to-brittle transitions temperature shift in Russian pressure vessel steels is delivered by mechanisms other than radiation hardening.

Keywords:
reactor pressure vessel steels, radiation embrittlement, hardening, grain boundary segregation, innercrystalline segregation

Paper ID: STP13870S
Committee/Subcommittee: E10.07
DOI: 10.1520/STP13870S
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