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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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Institute of Nuclear Technology
Takumi Terachi
Institute of Nuclear Technology
Nuclear Power Plant Aging Research Center
Material Technology Group
Research Articles
202027159174
SCC initiation in cold worked Alloy TT690 under simulated PWR primary water(2nd report) - Crack initiation under high stress condition allowing plastic deformation –
201926118135
SCC initiation in cold worked Alloy TT690 under simulated PWR primary water
201825187208
Current Knowledge and Future Challenges on SCC in Alloy 690 TT
201724090100
Influence of Hydrogen Gas on PWSCC of Cold Worked Alloy 690
201623060069
Study on PWSCC initiation condition on cold worked Alloy 690 using SSRT
201522129139
The Infl uence of Grain Boundary Cavity Formation on the SCC Growth Rate of Alloy 690
201118137151
Role of Grain Boundary Oxidation on PWSCC Initiation Influence of Chemical Compositions and Stress
201017130149
Mechanistic Study on SCC Propagation of Welded Nickel Based Alloy, (V) ―Corrosion Behavior under Deaerated High-Temperature Water―
200916146159
Basic Study on SCC of Stainless Steels in High-Temperature Water ―Temperature Dependence of Corrosion―
200815125140
Mechanistic Study on SCC Propagation of Welded Nickel based Alloy,(IV) ― Influence of Dissolved Hydrogen on Crack Tips ―
200714239252
Mechanistic Study on SCC Propagation of Welded Nickel based Alloy − Evaluation of Material Characteristics on Corrosion and Stress Condition −
200613179193
Stress Corrosion Cracking of Stainless Steel under Deaerated High-Temperature Water - Influence of Cold Work and Processing Orientation -
200512207216
Corrosion Behavior of Stainless Steels in High-temperature Water Environments ― Influence of Hydrogen and Oxygen Considerations for Initiation of SCC ―
200411153160
Influence of Water Chemistry Conditions and Cr Concentration on Oxide Film of SUS316 under High Temperature Water
200310151162
Analysis of IGSCC Crack Tip and Oxide Film on SUS 316 Generated under High Temperature Water
200209124135
Structural Analysis of Surface Film on Alloy 600 Formed under Environment of PWR Primary Water
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