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Institute of Social Research Articles

A Study on Safety Climate at Nuclear Power Plants
A Survey Study about What an Exhibition Hall of Nuclear Power Station Should be
How do residents in the Reinan district perceive their quality of life ?
Choice of Future Energy Resources : How Much Will Photovoltaic Generation Systems Cost to Japanese
Relationship between People’s Awareness of Environmental Capabilities of Saving Energy, Photovoltaic Power Generation and Nuclear Power Generation
A Study on the Role of Nuclear Energy in the Demand-Supply Structure in the 21st Century ― Towards the use of hydrogen and electricity energy －

Institute of Nuclear Technology Articles

Development of a New Model to Evaluate the Probability of Automatic Plant Trips for Pressurized Water Reactors
Sensitivity Study of Buckling Strength for Cylindrical Shells
Evaluation methods of Vibration Stress of Small Bore Piping
Initiation and Propagation of Multiple Cracks of Stainless Steel in High Temperature Water Environment
Influence of Dissolved Hydrogen on Oxide Film and PWSCC of Alloy 600 in PWR Primary Water
Influence of Deformation on SCC Susceptibility of Austenitic Stainless Steel in PWR Primary Water
Influence of Thermal Aging on Primary Water Stress Corrosion Cracking of Cast Duplex Stainless Steels
Stress Corrosion Cracking of Highly Irradiated 316 Stainless Steels
Characterization of SCC Crack Tip and Hydrogen Distribution in Alloy 600
Investigation of Neutron Irradiated Reactor Vessel Steels using Post-irradiation Annealing Techniques
Swelling i n Cold-worked 316 Stainless Steels irradiated in a PWR
Evaluation of Material Property of Austenitic Stainless Steel using Nano-Indentation
Design Study on Dose Evaluation Method for Employees at Severe Accident
Evaluation of Effectivoness of Inservice Inspection in Aging PWR Plants based on PSA
Analyses of Plant Behaviors at the Secondary Side Depressurization during LOCA of PWR
Development of Heat Transfer Models for Gap Cooling

Document

Analysis of Failure Events for Expansion Joints in Nuclear Power Plants
Development of Graphic Display Program of Reactor Operating Parameters for Emergency Exercise at Nuclear Power Plants
Investigation of Impingement Attack Mechanism of Copper Alloy Condenser Tubes

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