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Institute of Nuclear Technology
Working 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
Staff
Institute of Nuclear Technology
Masayuki Kamaya
Institute of Nuclear Technology
Nuclear Power Plant Aging Research Center
Thermal Hydraulics and Mechanics Group
Leader
Research Articles
202330070086
Causes of Evolution and Influence on Failure Strength of Thermal Crazing
202229089103
Influence of Plastic Strain on Fatigue Damage Assessment for Seismic Load
202128245263
Ways of Obtaining J-integrals for Assessment of Cracked Components
202027096104
Development of reliability assessment model for seismic loading that considers fatigue damage
201926066077
An axial crack growth prediction procedure initiated at butt welded joint (Growth prediction for surface crack deeper than semi-circular and that retarded at weld fusion line)
201825051062
Optimization of inspection interval by applying performance based maintenance concept(Assessment of change in failure probability by probabilistic fracture mechanics)
201724074080
Crack Growth Prediction for Low-Cycle Fatigue Regime
201623030043
Load carrying capacity assessment of cracked components by elastic-plastic fi nite element analysis (Investigation of load carrying capacity assessment procedures for stainless steel plates and pipes)
201522055070
Structural integrity of stainless steel components exposed to neutron irradiation (Change in failure strength of cracked components due to cold working)
201421170184
Procedures for obtaining stress-strain curve including post-necking strain (Applicability of testing method(IFD method)and estimation method(K-fi t method) for stainless steels)
201320191203
Influence of Mean stress on Fatigue Strength of Stainless Steel
201320157170
Damage Assessment of Low-cycle Fatigue by Crack Growth Prediction (Fatigue Life under Cyclic Thermal Stress)
201219166182
Damage Assessment of Low-cycle Fatigue by Crack Growth Prediction (Development of Growth Prediction Model and its Application)
201118181197
Damage Measurement of Structural Material by Electron Backscatter Diffraction (Quantification of measurement quality toward standardization of measurement procedure)
201017159171
Damage due to Low-cycle Fatigue of Type 316 Stainless Steel ―Fatigue Life under Variable Loading and Influence of Internal Cracks―
200916179188
Effect of Plastic Strain on Fracture Strength of Cracked Components
200815204216
Mechanism and Influence of Evolution of Crack Network under Thermal Fatigue Loading
200714253265
Measurement of Crystal Misorientation Distribution by Electron Backscatter Diffraction
200613128136
Evaluation of Local Stress at Grain Boundaries by Three-Dimensional Polycrystalline Model
200512222229
Observation and Prediction of "Initiation Dominant Growth" due to Stress Corrosion Cracking in Type 304 Stainless Steel in High Temperature Water
200411161172
Measurement of Plastic Strain of Polycrystalline Material by Electron Backscatter Diffraction
200310175185
A Simulation on Growth of Multiple Small Cracks under Stress Corrosion
200209136143
Effect of Elastic Anisotropy of Crystal Grain on Stress Intensity Factor
200108100110
Initiation and Propagation of Multiple Cracks of Stainless Steel in High Temperature Water Environment
200007137144
Development of Crack Propagation Simulation Model Considering the Interaction of Multiple Cracks
Institutes
Institute of Social Research
Research Center for Human Factors
Human Behavior Research Group
Organization and Culture Research Group
Research Project for Social Awareness and Energy Issues
Institute of Nuclear Technology
Nuclear Power Plant Aging Research Center
Thermal Hydraulics and Mechanics Group
Material Technology Group
Nuclear Power Information Research Project
Nuclear Safety and Emergency Support Research Project