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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

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