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
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Staff

Institute of Nuclear Technology

Akira Nakamura

Institute of Nuclear TechnologyNuclear Safety and Emergency Support Research Project

Research Articles

202128141150 Estimation development using support vector machine to evaluate the break diameter during PWR loss-of-coolant accident
201522213224 A review of evaluation methods developed for numerical simulation of the temperature fl uctuation contributing to thermal fatigue of a T-junction pipe
201320038044 Effect of Pipe Shapes on Penetration Length in a Closed Straight Branch Pipe
201219039049 Evaluation of Penetration Length in a Closed Straight Branch Pipe Using Numerical Simulations
201118056068 Numerical Simulations of Thermal Striping at T-junction Pipe ― 2nd Report : The Effects of LES Model Parameters and Temperature Diffusion Schemes ―
200815078087 The Effect of Local Flow Field on Flow Accelerated Corrosion − The Background of the Research and Measurements of Corrosion Rate after an Orifice−
200714099115 Numerical Simulations of Thermal Striping at T-junction Pipe − The Effect of Turbulence Model and Computational Grid −
200613102114 An Approach of Integrated Evaluation Method for Thermal Fatigue II － A Validation of Evaluation Method by Numerical Simulations －
200512146153 Investigation of Flow Structure and Temperature Fluctuations in a Straight Branch Pipe with Closed End
200209067079 Experiments and Numerical Simulations of Fluctuating Thermal Stratification in a Branch Pipe
200007201215 Flow-induced Vibration of a Circular Cylinder