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RISBayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The goal of this study was to identify the chemical component variables that should be used in irradiation embrittlement prediction and to determine the uncertainty of prediction of irradiation embrittlement of reactor ...
Bayesian Approach to Model Temperature Dependence of Charpy Absorbed Energy and Uncertainty Evaluation of Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Abstract. Embrittlement of reactor pressure vessel (RPV) steel caused by neutron irradiation has been evaluated using ductile-to-brittle transition temperature (DBTT) derived from surveillance tests (Charpy impact tests) ...
Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The applicability of miniature compact tension (Mini-C(T)) specimens to fracture toughness evaluation of neutron-irradiated reactor pressure vessel (RPV) steels was investigated. Three types of RPV steels neutron-irradiated ...
Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: We conducted fracture toughness testing on five types of commercially manufactured steel with different ductiletobrittle transition temperatures. This was performed using specimens of different sizes and shapes, including ...