株式会社原子力安全システム研究所 > about　INSS > INSS Journal > INSS Journal 2014 Vol.21

back to INSS Journal＞＞

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

Review

Development of Incident Progress Prediction Technologies for Nuclear Emergency Preparedness – Current Status and Future Subjects –
Research Activities of the INSS Institute of Nuclear Technology from FY2008 to FY2013 and Future Policy

PAGE TOP