Naoto Kasahara

Development of Constitutive Models for Fast Reactor Design - Strategy of the study and results in the first half stage -

Study on Mechanical Behavior of Weldments of Type 304SS under Creep-Fatigue Loading

OS0614-144 Cyclic Plasticity Constitutive Equations for Carbon Steel and Benchmark Analyses of Piping Structures

122 The Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Hydrogen Concentration in the

OS1510 Creep-fatigue evaluation of a structural model made of Mod.9Cr-1Mo steel subjected to the cyclic thermal loading

F112 Development of Failed Fuel Detection and Location System in Sodium-Cooled Large Reactor : Sampling method of failed fuels under the slit

017 Development of Evaluation Method based on Inelastic Analyses for Structural Design of Fast Reactor Components : (1) Guidelines for Inelastic Design Analysis

1128 Validation for the creep-fatigue evaluation method under intermediate hold conditions by the tests on the liquid-surface model

020 Development of Evaluation Method based on Inelastic Analyses forStructural Design of Fast Reactor Components : (4) Examples of Design Analyses by Use of the Guidelines

018 Development of Evaluation Method based on Inelastic Analyses for Structural Design of Fast Reactor Components : (2) Summary of Recommended Inelastic Constitutive Models