Irradiation embrittlement of reactor pressure vessel steels due to mechanisms other than radiation hardening

Conference · Fri Oct 01 04:00:00 EDT 1999

OSTI ID:679491

Gurovich, B A; Korolev, Y N; Kuleshova, E A; Nikolaev, Y A; Shtrombakh, Y I ^[1]

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1. Russian Research Center Kurchatov Inst., Moscow (Russian Federation). Reactor Materials Div.

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 them 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.

• OSTI ID: 679491
• Report Number(s): CONF-960643--
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
ANNEALING
DUCTILE-BRITTLE TRANSITIONS
EMBRITTLEMENT
GRAIN BOUNDARIES
MECHANICAL TESTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR MATERIALS
SEGREGATION
STEELS