INSS JOURNAL21 2014
Institute of Social Research Articles
- Study on Reinforcing the Safety Climate Survey －Based on International Perspectives on Safety Culture－
- Development and improvement of the self-assessment system for reduction of information security accidents in call center operation
- People’s awareness toward power generation choices － Two and a half years after the Fukushima Daiichi Nuclear Power Plant accident －
- Research on the response of various persons to information about nuclear power generation
- The Change of Thinking about Science by Children in Fukui Prefecture
Institute of Nuclear Technology Articles
- Development of an On-Site Measurement Method for Residual Stress in Primary System Piping of Nuclear Power Plants
- Seismic Response Evaluation for Piping Systems with Support Structures （Eff ect of Input Acceleration Amplitude on Resonance Frequency and Response Reduction in the Elastic Vibration Test）
- An Investigation of Characteristics of Thermal Stress Caused by Fluid Temperature Fluctuation at a T-Junction Pipe
- Eff ects of Local Flow Field on Flow Accelerated Corrosion -Wall Thinning Rate at Elbow Pipe-
- Atom Probe Tomography Characterization of Neutron Irradiated Austenitic Stainless Steel
- Eff ects of Helium on Grain Boundary Fracture of Neutron-irradiated Stainless Steel,（II） - Synergistic Eff ects with Radiation-induced Segregation -
- SCC growth behavior of cold worked alloy 690 in high-temperature water －Dependence of test temperature, dissolved hydrogen in water, grain boundary carbide and chemical composition－
- The conditions for changing from SCC initiation to growth in stainless steel
- PWSCC crack growth rate of alloy 690 to simulate actual plant material
- An Evaluation of depth sizing ability of ultrasonic testing by the large aperture transducer for axial crack in cast stainless steel pipe weld
- Procedures for obtaining stress-strain curve including post-necking strain （Applicability of testing method（IFD method）and estimation method（K-fi t method） for stainless steels）
- Transient evaluation using EMTP at one phase opening of the off site power transformer of the emergency power supply systems for nuclear power plants （This report is a follow-up the last year’s.）
- Development and application of the practice tool to deal with severe accident
- Analysis and Evaluation for Main Steam Line Break Accident in PWR
- Application of the Best Estimate Plus Uncertainty method to the small break LOCA with high pressure injection failure : Uncertainty quantifi cation of the RELAP5 model related to fuel clad oxidation, decay heat, fuel clad deformation and SG U-tube condensation