ホームabout INSSINSS JournalINSS Journal 2010 Vol.17 INSS Journal 2010 Vol.17 back to INSS Journal＞＞ Institute of Social Research Articles Peopleʼs response to the promotion of the effective use of nuclear power plants ―From the viewpoint of favoring providing information about maintenance activities―A study on the effect of context on peopleʼs perception of a small radiation leak at a nuclear power plantSocial Acceptance for Seismic Safety of Nuclear InstallationsFactors Constituting Trust in Public Utilities ―Comparison between Public Utilities and Private Companies―The Development of Teaching Materials for Energy and Environmental Education Integrated into Main Subjects in Schools Institute of Nuclear Technology Articles Fast Computable Residual Stress Analysis for Welded Pipe Joint Based on Iterative Substructure MethodInvestigation of Wall Temperature Fluctuations by Visualization Tests and Numerical Simulation for Steam-Water Two-phase flow in the Pressurizer Spray PipingLDV measurements and URANS calculations downstream of a globe valveEffects of Local Flow Field on Flow Accelerated Corrosion ―Effect of Flow Velocity on Corrosion Rate―Development of Method to Measure Vibrational Stress of Small-Bore Piping with Multiple Contactless Displacement Sensors ―Vibration Test to Apply the Proposed Method to Practical Use―Effect of Dissolved Hydrogen Concentration on PWSCC Crack Growth Rate of Alloy 600 at 290℃Mechanistic Study on SCC Propagation of Welded Nickel Based Alloy, (V) ―Corrosion Behavior under Deaerated High-Temperature Water―SCC growth behavior of stainless steel weld heat-affected zone in hydrogenated high temperature waterDamage due to Low-cycle Fatigue of Type 316 Stainless Steel ―Fatigue Life under Variable Loading and Influence of Internal Cracks―Development ofmicro tensile testing method in an FIB system for evaluating grain boundary strengthEffects of hydrogen on interaction between dislocation and radiation-induced defectsFIB sequential sectioning as a tool to understand environmental materials degradation in 3DA Study ofNon Destructive Integrity Assessment Method for Structural Materials ofNuclear Reactor -Part 1-A Proposal for a Determination Method of Element Division on an Analytical Model for Finite Element Elastic Waves Propagation AnalysisResearch and Analysis of On-line Maintenance Process and Problems at United States Nuclear Power PlantsInvestigation of Practical Use Situation and Performance for Electric Transient Analysis Programs in the U.S. Nuclear Power PlantsTrend Analysis of Troubles Caused by Thermal-Hydraulic Phenomena at Nuclear Power PlantsFeasibility Study of Computerized Presentation of Procedures of a Nuclear PlantTrend Analysis of the Adverse Event Cause in Nuclear power plantsStudy on Examples of Safety Culture Enhancing Activities at U.S. Nuclear Power StationsMain Steam Line Break Accident Analysis for 4-Loop PWR Plant by RELAP5-3D CodePlant Incident Progress Scenario Analysis for Nuclear Emergency Exercise of Fukui Pref. 2009 Comments The Research Project on Technical Information Basis for Aging Management in Fukui and Kinki Area (3rd Report)Study on Counter-Current Flow in a PWR Hot Leg under Reflux CondensationA concern about the crack propagation rate of PWSCC which obtained from the investigation on primary coolant leakage portion of the reactor vessel head in Ohi 3
