0000-0003-4465-7330 Employment
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Institute of Nuclear Safety System, Incorporated Senior Researcher
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Publications (67)
- Intergranular oxidation behaviors of Alloy 600, TT Alloy 690 and 316 stainless steel under simulated PWR primary water conditions Save
- TT690 合金の SCC 進展速度に及ぼす温度の影響 Influence of Temperature on SCC Growth Rate in Alloy 690TT Save
- TECHNICAL BASIS FOR JSME CODE CASE ON STRESS CORROSION CRACK GROWTH RATES OF STAINLESS STEELS IN PWR ENVIRONMENTS Save
- Deformation band corrosion as a result of applied stress and cold-work in 304 stainless steel in simulated pressurized water reactor primary water conditions Save
- Influence of composition and temperature on oxide film formation for Fe-Cr-Ni alloys in simulated PWR primary water Save
- PWR1次系模擬水中におけるTT690合金冷間加工材のSCC発生評価(第4報) -微小亀裂の成長挙動- SCC Initiation in Cold Worked Alloy 690 TT under Simulated PWR Primary Water (4th Report) – Growth Behavior of Microcracks – Save
- INTER-GRANULAR STRESS CORROSION CRACKING IN THE HEAT AFFECTED ZONE OF THE PRESSURIZER SPRAY LINE PIPING OF A PRESSURIZED WATER REACTOR Save
- On the role of intergranular nanocavities in long-term stress corrosion cracking of Alloy 690 Save
- PWR1次系模擬水中におけるTT690合金冷間加工材のSCC発生評価（第2報）-変形を許容した高応力条件下での亀裂発生挙動- SCC initiation in cold worked Alloy TT690 under simulated PWR primary water (2nd report)- Crack initiation under high stress condition allowing plastic deformation- Save
- Morphology of cavities formed on grain boundary of cracked alloy TT690 Save