ホームabout INSSINSS JournalINSS Journal 2017 Vol.24 INSS Journal 2017 Vol.24 back to INSS Journal＞＞ 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 workChange 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 RegimeStudy 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 690SCC Growth Behavior of SUS630 in High-Temperature WaterInfluence of Solute Elements on Radiation Embrittlement of Reactor Vessel SteelsCharacterization 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 EnvironmentAnalysis of License Renewal at U.S. Nuclear Power PlantsTrend Analysis of pump Failure Events at U.S. Nuclear PlantsStudy 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 PrefecturePreliminary 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 PipesUncertainty Quantifi cation of the RELAP5 Interfacial Friction Model in the Rod Bundle GeometryA Review of the Study on Counter-Current Flow Limitation at the Lower End of Heat Transfer Tubes in a Steam GeneratorThe Historical Process and Method Overview of the Statistical Safety Evaluation Full text
