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Irradiation embrittlement of reactor pressure vessel steels is usually predicted based on ductile-to-brittle transition temperature shift obtained by Charpy impact tests for unirradiated and irradiated specimens. It is important to understand the uncertainty in the evaluation by Charpy impact test when giving margins for structural integrity assessment using embrittlement trend curves and when discussing the need for surveillance specimens obtained from the weld heat affected zone. In this study, we modeled the temperature dependence of Charpy absorbed energy based on about 1900 datasets of unirradiated and irradiated Japanese and U.S. materials. Then we used Bayesian statistics to construct an evaluation model that could take into account the variation in absorbed energy, the number of tests, and test temperatures for each dataset. In my presentation, we will discuss the results of analyses for the effects of irradiation, difference between Japanese and U.S. materials, and product form on the uncertainty of the Charpy ductile-to-brittle transition temperature.

Oral presentation

Study on uncertainty in the evaluation of reactor pressure vessel embrittlement by Charpy impact testing

Takamizawa, Hisashi

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no abstracts in English

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Bayesian uncertainty evaluation of Charpy ductile-to-brittle transition temperature for reactor pressure vessel steels

Evaluation of neutron irradiation embrittlement in structural materials for reactor pressure vessel

Comparison of transition temperature shifts between static fracture toughness and Charpy-V impact properties due to irradiation and post-irradiation annealing for Japanese A533B-1 steels

Development of reconstitution technique of irradiated speciments, 3; Report for FY 1995 and FY 1996 on JAERI-IHI cooperated research program (Joint research)

Development of reconstitution method for surveillance specimens using surface-activated joining

Development of reconstitution technique of irradiated specimen, II; Annual report for FY1994 on JAERI-IHI cooperated research program

Application of solid state diffusion bonding to fusion reactor

Surface-activated joining,reconstitution technique of surveillance specimens

The Surveillance Test of a Light Water Cooled Nuclear Power Reactor,Part I; The Present and Some Questions

Uncertainty evaluation of Charpy ductile-to-brittle transition temperature for neutron-irradiated reactor pressure vessel steels

Uncertainty evaluation of Charpy ductile-to-brittle transition temperature

Uncertainty evaluation of Charpy ductile-to-brittle transition temperature using Bayesian inference

Study on uncertainty in the evaluation of reactor pressure vessel embrittlement by Charpy impact testing