SYMPOSIA PAPER Published: 01 January 2000

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


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.

Author Information

Nikolaev, YA
Russian Research Center “Kurchatov Institute”, ORM, Moscow, Russia
Nikolaeva, AV
Nuclear Safety Institute, Russian Academy of Sciences, Moscow, Russia
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Developed by Committee: E10
Pages: 460–470
DOI: 10.1520/STP12408S
ISBN-EB: 978-0-8031-5419-3
ISBN-13: 978-0-8031-2852-1