Search
CSV
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) ...
Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The fracture toughness in the heat-affected zone (HAZ), which is located under the weld overlay cladding on the inner surface of the reactor pressure vessel (RPV), was evaluated by considering the inhomogeneous microstructures ...
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 ...