SYMPOSIA PAPER Published: 01 January 1999
STP13870S

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

Source

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.

Author Information

Gurovich, BA
Reactor Materials Division Russian Research Center “Kurchatov Institute”, Moscow, Russia
Korolev, YN
Reactor Materials Division Russian Research Center “Kurchatov Institute”, Moscow, Russia
Kuleshova, EA
Reactor Materials Division Russian Research Center “Kurchatov Institute”, Moscow, Russia
Nikolaev, YA
Reactor Materials Division Russian Research Center “Kurchatov Institute”, Moscow, Russia
Shtrombakh, YI
Reactor Materials Division Russian Research Center “Kurchatov Institute”, Moscow, Russia
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Details
Developed by Committee: E10
Pages: 271–295
DOI: 10.1520/STP13870S
ISBN-EB: 978-0-8031-5395-0
ISBN-13: 978-0-8031-2614-5