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Institute of Nuclear Technology Articles

Flow Structure in a Downward Branch Pipe with a Closed End (Eff ect of Branch Pipe Shapes on Flow Structure)
Structural integrity of stainless steel components exposed to neutron irradiation (Change in failure strength of cracked components due to cold working)
Numerical Simulations of Thermal Striping at T-junction Pipe - 3rd Report: The Eff ects of Inlet Boundary Conditions on Temperature Fluctuation Intensity -
APT analysis of stainless steel welds after long-term thermal aging and neutron irradiation
Corrosion of irradiated stainless steels in simulated PWR primary water(2)
Corrosion Behavior of Ion-irradiated Stainless Steel in Simulated PWR Primary Water
SCC Growth Behavior of alloy 182 and 152 /SUS316 dissimilar metal weld joints in High-Temperature Water
The Infl uence of Grain Boundary Cavity Formation on the SCC Growth Rate of Alloy 690
A Feasibility Study of Evaluating Irradiation Embrittlement of Low Alloy Steel using Thermoelectric Power
Transient evaluation using EMTP at one phase opening with the off site power transformer for the emergency power supply systems of nuclear power plants (This report is a follow-up of the report published two years ago.) -Verifi cation related to the open-phase detection method of the transformer by United States Electric Power Research Institute(EPRI)-
Trend Analysis of Motor Operated valve actuating device Failure Events at U.S.Nuclear Plants
Plant Incident Progress Scenario Analysis for the FY2014 Nuclear Emergency Exercise of Fukui Prefecture
Application of the Best Estimate Plus Uncertainty method to the small break LOCA with high pressure injection failure: Eff ect evaluation of the model uncertainty on the safety evaluation parameter

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