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

Takumi Terachi

Institute of Nuclear TechnologyNuclear Power Plant Aging Research CenterMaterial Technology Group

Research Articles

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