SEDL / STP / STP1366-EB / STP12404S



Comparison of Observed and Predicted Data on Radiation Induced Grain Boundary Phosphorus Segregation in VVER Type Steels

Nikolaeva, AV
Senior research scientist, Nuclear Safety Institute, Russian Academy of Sciences, Moscow

Kevorkyan, YR
Leading research scientists, Russian Research Center “Kurchatov Institute”, ORM, Moscow

Nikolaev, YA
Leading research scientists, Russian Research Center “Kurchatov Institute”, ORM, Moscow


Pages: 13    Published: Jan 2000


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Abstract

The influence of impurity grain boundary segregation on mechanical properties of low-alloy Cr-Ni-Mo steels is discussed. Mechanisms of impurity and alloying effects on grain boundary embrittlement of low-alloy steels are considered. An approach for estimation of radiation enhanced grain boundary segregation kinetics is proposed. The approach takes into account the reduction of dislocation density (from 1×1014 to 1×1013 m-2) due to irradiation that was observed for low-alloy Cr-Ni-Mo steels. The influence of collision cascades on the radiation damage is also considered. Auger spectroscopy is used for grain boundary segregation detection. The contribution of grain boundary embrittlement to mechanical property degradation due to neutron irradiation is assessed.


Keywords:
reactor pressure vessel, grain boundary segregation, radiation embrittlement, ductile-to-brittle transition temperature

Paper ID: STP12404S
Committee/Subcommittee: E10.08
DOI: 10.1520/STP12404S
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