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Institute of Social Research Articles

The Impact of Events Related to Nuclear Power Plants on Staff　– An Overview Based on Safety Climate Survey Responses —
Age Differences in Safety Climate Assessment of Nuclear Industry Employees
“Does a Focus on Risks Change Young People’s Attitude Towards Nuclear Power Generation?”
People’s Attitudes toward Achieving Carbon Neutrality in 2050
Risk Communication in Energy Issues — What it means to show a willingness to thinking together —
Measuring Science and Technology Literacy in Social Surveys: Evaluation of Factual Judgments about Energy Issues and Nuclear Power Generation

Institute of Nuclear Technology Articles

Causes of Evolution and Influence on Failure Strength of Thermal Crazing
Fatigue Life Assessment for Variable Strain in a Mixing Tee by Use of Effective Strain Range
Effect of Si on Solute Atom Clustering in Reactor Vessel Steels
Visualization of a Stress Corrosion Cracking in Ni Based Alloy Weldment
Evaluation of grain boundary cavity distribution of a creep tested cold worked Alloy 690TT specimen and its correlation with stress distribution of the specimen
Evaluation of Grain Boundary Segregation in Neutron-irradiated Stainless Steel by Electron Microscopy and Atom Probe Tomography
Influences of dissolved hydrogen on corrosion behavior of Alloy 690 TT in zinc-injected simulated PWR primary water condition
Evaluation of the formation of fine particles in the 6061-aluminum alloy by the second harmonic measuring method
Configuration Management Learning from Operation Experience Analysis
Analysis based on Mihama emergency exercise scenario of Kansai Electric Power Co., Inc. 2022
Effects of Liquid Viscosity on Flow Characteristics in a Vertical Pipe under Flooding Conditions
Application of Surrogate Models for Statistical Safety Evaluation （Bayesian inference for uncertainty analysis of PWRs）
Numerical Simulation of Gas-Liquid Counter-Current Flow in a Vertical Pipe with Rounded Top and Bottom Ends
Wall Condensation from Saturated Steam-Air Mixture in Natural Convection
Numerical Simulation with the GOTHIC Code for a Wall Condensation Experiment Using a Flat Plate

Review

SCC growth behavior in weld HAZ of austenitic stainless steels in a simulated PWR primary water – Current research status and future program –

Document

Actions to Make the Company a Great Place to work：Classification by Text Mining
Status of Telework During the Mitigation Phase of COVID-19 Pandemic Infection Control
Trends in Public Opinion Concerning Nuclear Power Generation in the United States and Europe after the Fukushima Daiichi Power Plant Accident（6）
The production of digital teaching materials incorporating the perspective of energy and environmental issues（1）
Investigation of Damages by Deadly Weather Conditions to Areas of Surrounding NPPs in USA

Comments

Integral Effect Tests on Core Fuel Damage and Relocation under Severe Accident Conditions

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