Institute of Social Research Articles

• Development of Emergency Response Training focusing on non-technical skills　-（1）Development and Trial of “TAIKAN Training” -
• Development of Emergency Response Training focusing on non-technical skills　-（2）Extraction of Non-Technical Skills -
• Restrictive Mechanism for Safety Behaviors and Safety Attitudes　- An Analysis Focusing on Confi dence in Skills and Knowledge -
• Study of the development of a safety culture by describing routine work
• Change in Perception of People towards a Nuclear Emergency Plan for a Nuclear Power Station after Being Presented

Institute of Nuclear Technology Articles

• Crack Growth Prediction for Low-Cycle Fatigue Regime
• Study on Characteristics of Wall Temperature Fluctuation at a Mixing Tee （Eff ect of Upstream Elbow）
• Influence of Hydrogen Gas on PWSCC of Cold Worked Alloy 690
• SCC Growth Behavior of SUS630 in High-Temperature Water
• Influence of Solute Elements on Radiation Embrittlement of Reactor Vessel Steels
• Characterization of Grain Boundary Fracture in Neutron-irradiated Stainless Steel by Micro-Tensile Testing - Comparison between Baffl e Former Bolt and Flux Thimble Tube -
• Irradiation Dose Dependence of Grain Boundary Oxidation of Neutron Irradiated Stainless Steel in Simulated PWR Primary Water Environment
• Analysis of License Renewal at U.S. Nuclear Power Plants
• Trend Analysis of pump Failure Events at U.S. Nuclear Plants
• Study on Dose Calculation Method for Operational Intervention Level - Evaluation of the Intake of Foods and Drinks for OIL6 -
• Plant Incident Progress Scenario Analysis for the FY2016 Nuclear Emergency Exercise of Fukui Prefecture
• Preliminary Study on Numerical Simulations for Temperature Field of Steam-Air Mixture in a Circular Tube with Condensation

Review

• Safety climate and safety culture:　On concept, measurement and theory, and fostering

Document

• Trends in Public Opinion Concerning Nuclear Power Generation in the United States and Europe after the Fukushima Daiichi Power Plant Accident（3）

Comments

• Counter-Current Flow Limitation in Nearly Horizontal Pipes
• Uncertainty Quantifi cation of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
• A Review of the Study on Counter-Current Flow Limitation at the Lower End of Heat Transfer Tubes in a Steam Generator
• The Historical Process and Method Overview of the Statistical Safety Evaluation