ホームabout INSSINSS JournalINSS Journal 2022 Vol.29 INSS Journal 2022 Vol.29 back to INSS Journal＞＞ Institute of Social Research Articles Overview and application of the causal analysis method “ATOP”The Relationship between Information Transmission in Organizations and Trust in SuperiorsA Discussion of the Relationship Between Resources and Safety CultureThe Effect of Safety Climate on the Number of Accidents at Nuclear Power Plants：Analysis with Generalized Linear Mixed ModelAn Exploration for Changes in Electricity Consumers：Free-response statements regarding Lifestyle Changes during the Covid-19 PandemicRisk communication in energy issues －What it means to show a willingness to thinking together（Preliminary survey）－Risk communication in energy issues －The difference of explicitly presenting two-sided messages（Preliminary sutdy）－Interview survey on perception of people towards information about interim storage facilities for spent nuclear fuel Institute of Nuclear Technology Articles Influence of Plastic Strain on Fatigue Damage Assessment for Seismic LoadProposal of fatigue assessment method for piping under seismic loading （About the use of effective strain range for loading sequence effect）Effect of Ni on Solute Atom Clustering in Reactor Vessel SteelsHigher harmonic imaging of stress corrosion cracking using a direct contact techniqueSCC Growth Behavior of Stainless Steel Weld Metals in Oxygenated High －Temperature Water -Influence of Thermal Aging, Temperature and Water Chemistry－SCC initiation in cold worked Alloy 690TT under simulated PWR primary water（3rd report）－Crack initiation of cavity induced specimens prior to SCC initiation test－An examination of k-factor in TEM-EDS analysis for grain boundary segregation in neutron-irradiated stainless steelsInfluences of dissolved hydrogen and temperature on corrosion behavior of Stellite Alloy in a simulated PWR primary water conditionA trial analysis of license event reports（LERs）of U.S. nuclear power plants by text miningFlow characteristics in a rod bundle under gas-liquid counter-current flowsFuel cladding temperature behavior in a reactor core during severe accidentVerification on correlation of wall friction factor for falling liquid film in vertical pipesApplication of surrogate models for statistical safety evaluation（Bayesian modeling and inference for uncertainty analysis using Stan）Plant incident progress scenario analysis for Mihama nuclear emergency exercise of Kansai Electric Power Co., Inc. 2021 Document Trends in Surveys about Home Teleworking During the COVID-19 Pandemic in Japan（2）－From Teleworking to Hybrid Workin－Have the problems of teleworking been overcome?Trends in Public Opinion Concerning Nuclear Power Generation in the United States and Europe after the Fukushima Daiichi Power Plant Accident（5）Results of the questionnaire survey on practice of energy and environmental education at school sitesChallenges toward Gender Balance in the Nuclear Industry Comments The development status of RELAPEfforts to investigate long-term aging effect utilizing a harvested carbon steel material from a replaced componentDatabase on irradiation effects of stainless steels in light water reactors Full text INSS Journal 2022 vol.29 Full text
