INSS JOURNAL14 2007
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