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Institute of Social Research Articles

Factors that contribute to making the rules a dead letter in the workplace
The Effect of Pointing and Calling on the Inhibition of the Disturbing Sounds
Effects of pointing action on visuo-spatial learning
Prerequisites of ideal safety-critical organizations
The trend of the Public Opinion upon Nuclear Power Generation in Internet Blog
Promoting Program for Energy and Environmental Education in Schools

Institute of Nuclear Technology Articles

Numerical Simulations of Thermal Striping at T-junction Pipe ― 2nd Report : The Effects of LES Model Parameters and Temperature Diffusion Schemes ―
Welding Simulation of Large-Diameter Thick-Walled Stainless Steel Pipe Joints ― Fast Computation of Residual Stress and Influence of Heat Source Model ―
Effects of Local Flow Field on Flow Accelerated Corrosion ― Corrosion Rate downstream of a Globe Valve ―
Effects of Local Flow Field on Flow Accelerated Corrosion ― Relation between the FAC Rate and the Wall Shear Stress Downstream from an Orifice ―
Measuring of Wall Temperature to Investigate Thermal Fatigue at a T–Junction Pipe ― A Study on the Temperature Measuring Method Using Thermocouples ―
Effect of Elastic-Plastic Property of Support Structure on Seismic Response of Piping System
Investigation on a Predicting Method for Vibration Response and Vibration Fatigue in Small-Bore Piping
Role of Grain Boundary Oxidation on PWSCC Initiation Influence of Chemical Compositions and Stress
Effects of Dissolved Hydrogen on IASCC Initiation
SCC Growth Behavior of Cast Stainless Steels in High-Temperature Water ― Influences of Corrosion Potential, Steel Type, Thermal Aging and Cold-Work ―
A Study of Non Destructive Integrity Assessment Method for Structural Materials of Nuclear Reactor － Part 2 －
Damage Measurement of Structural Material by Electron Backscatter Diffraction （Quantification of measurement quality toward standardization of measurement procedure）
Development of a Tensile Testing Device under Ion Irradiation and Study on Effect of Stress on Radiation Embrittlement
A study for effects of grain size on occurrence of IASCC ― Effects of grain size on localized deformation of irradiated stainless steel ―
Development of an Ultrasonic Testing Technique to Inspect Corrosion on Containment Vessel Plates Embedded in Concrete of a Nuclear Power Plant（ IV） ― Evaluation of Ultrasonic Transducer Output by Numerical Analysis ―
Influence of Chemical Composition on Thermoelectric Power of Iron-based Alloy
A Study of Operation of Station Fire Brigade with Comparison for Japan and the U.S.
A Study on Activities of Nuclear Stations in the U.S. in the Aim of Enhancing Safety Culture
Trend Analyses of the Emergency Diesel Generator Problem Events in Japanese and U.S. Nuclear Power Plants
Trend Analysis of trouble event of domestic Nuclear Plants concerning vibration
Study of containment radiation dose for emergency protection zone prediction
COBRA-EN code/EPRI correlation-style DNBR calculation reliability evaluation
Development of the PIRT for the small break loss-of-coolant accident with high pressure injection failure and sensitivity analyses for important phenomena

Document

A Trend of the Public Opinion concerning Nuclear Power Generation in the United States and Europe after Fukushima Daiichi Power Plant Accident

Comments

The Research Project on Technical Information Basis for Aging Management in Fukui and Kinki Area（Final Report）

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