Institute of Nuclear TechnologyWorking to further enhance the safety
and reliability of nuclear power

Working to further enhance the safety and reliability of nuclear power

Institute of Nuclear Technology

Koji Miyoshi

Institute of Nuclear TechnologyNuclear Power Plant Aging Research CenterThermal Hydraulics and Mechanics Group

Research Articles

202330087098 Fatigue Life Assessment for Variable Strain in a Mixing Tee by Use of Effective Strain Range
202229104119 Proposal of fatigue assessment method for piping under seismic loading (About the use of effective strain range for loading sequence effect)
202128083094 Heat transfer coefficient suitable for thermal fatigue assessment at a T-junction
202027105116 Numerical Simulation of Thermal Stress Fluctuation at a Mixing Tee for Thermal Fatigue Problems
201926228250 Data for Validation to Improve Fluid-structure Thermal Coupled Simulation Methods at a Mixing Tee with Upstream Elbow
201825156173 Data for validation to improve fl uid-structure thermal coupled simulation methods at a mixing tee
201724081089 Study on Characteristics of Wall Temperature Fluctuation at a Mixing Tee (Eff ect of Upstream Elbow)
201623053059 Flow Structure in a Downward Branch Pipe with a Closed End (Characteristics of Flow Velocity in the Branch Pipe)
201522047054 Flow Structure in a Downward Branch Pipe with a Closed End (Eff ect of Branch Pipe Shapes on Flow Structure)
201421086098 An Investigation of Characteristics of Thermal Stress Caused by Fluid Temperature Fluctuation at a T-Junction Pipe
201320045055 An Investigation of Wall Temperature Characteristics to Improve Evaluation Method for Thermal Fatigue at a T-Junction Pipe
201118106117 Measuring of Wall Temperature to Investigate Thermal Fatigue at a T–Junction Pipe ― A Study on the Temperature Measuring Method Using Thermocouples ―
201017075087 Investigation of Wall Temperature Fluctuations by Visualization Tests and Numerical Simulation for Steam-Water Two-phase flow in the Pressurizer Spray Piping