SEDL / STP / STP1366-EB / STP12408S

Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels

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

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

Pages: 11    Published: Jan 2000

Download this paper for $25 PDF (188K)          View License Agreement
Abstract

Radiation embrittlement and its mitigation by annealing of VVER-440 reactor pressure vessel steels are studied. The Russian regulatory approach for prediction of radiation embrittlement of VVER-440 steels is considered. Results of an investigation of materials cut out of operating nuclear power plants are discussed. Different models of re-irradiation embrittlement are compared. A new model for assessment of embrittlement under re-irradiation is developed.