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Institute of Social Research Articles

Workplace Activities to Promote Small Attempts for Safety − Toward Development of Safety Culture in a Nuclear Power Plant −
Communication between organizations in a company − The influence of frontline workplace managersʼ communication on the personnelʼs evaluation of higher organization −
The Effective Communication Methodology and Influence of Merit Information on Nuclear Power
Effects of degree of approval and message on utility of nuclear fuel cycle
Study on Information Dissemination regarding Trouble at a Nuclear Power Plant
Activities encouraging the children to like science with the participation of science teachers in Fukui prefecture

Institute of Nuclear Technology Articles

Evaluation of Seismic Characteristics of Cylindrical Water Storage Tank by Vibration Test (4th Report) − Dynamic Buckling Experiment and Static Elastic-Plastic Buckling Analysis −
The visualization and CFD analysis of the flow in pressurizer spray line piping and calculation of thermal stress fluctuation caused by the swaying of water surface in the pipe
Numerical Simulations of Thermal Striping at T-junction Pipe − The Effect of Turbulence Model and Computational Grid −
Evaluation of Incipient Cavitation Erosion using Impact Force Detector and Accelerometer
Development of Method to Measure Vibrational Stress of Small-Bore Piping with Multiple Laser Displacement Sensors − Examination of Applicability by Error Analysis and Vibration Test Using a Plate −
Modeling of Dislocation Loop Formation and Radiation Induced Grain Boundary Segregation in Stainless Steels under Light Water Reactor Conditions
IASCC Properties and Mechanical Properties of Stainless Steel Irradiated to 73dpa in a PWR
Characterization of Deformation Structure in Ion-irradiated Stainless Steels
Role of Grain Boundary Diffusion of Vacancy on IGSCC Growth of Non-Sensitized Stainless Steels in High Temperature Water
Stress Corrosion Cracking of Stainless Steels under Deaerated High-Temperature Water − Influence of Grain Boundary Carbide Precipitation, and Effect of Mo and Cr in Alloys −
Novel Characterization of Stress Corrosion Cracks in Stainless Steels by NanoSIMS
Mechanistic Study on SCC Crack Propagation of Welded Ni based Alloy − An investigation of metallurgical factors of alloy 690 series −
Mechanistic Study on SCC Propagation of Welded Nickel based Alloy − Evaluation of Material Characteristics on Corrosion and Stress Condition −
Measurement of Crystal Misorientation Distribution by Electron Backscatter Diffraction
Influence of Ethanol-amine injection on Flow Accelerated Corrosion Rate in Pressurized Water Reactor
Measurement of Thermoelectric Power of Fe-Cu Binary Alloys
Influence of Array of Elements and of Measurement Condition with Twin Matrix Array Ultrasonic Transducer on Flaw Depth Measurement
New Method of Classifying Human Errors at Nuclear Power Plants and The Analysis Results of Applying this Method to Maintenance Errors at Domestic Plants
Trend Analysis of Cables Failure Events at Nuclear Power Plants
Comparison between Japan and the United States in the Frequency of Events in Equipment and Components at Nuclear Power Plants
Trend Analysis of Fire Events at Nuclear Power Plants
Analyses of Operating License Renewal for Nuclear Power Plants in USA
Development of a Rapid Prediction Technology of the Radioactivity Release Rate for Nuclear Emergency Preparedness
Behavior of Non-condensable Gas in Heat Transfer Tube Bundle of a Steam Generator during Reflux Condensation
RELAP5 Analysis of Reflux Condensation Behavior in Heat Transfer Tube Bundle of a Steam Generator
Development of Quick Calculation Method for Gamma-Ray Skyshine Dose

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