2020 Fall Meeting

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Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[1C05-09] Corrosion

Wed. Sep 16, 2020 3:55 PM - 5:15 PM Room C (Zoom room 3)

Chair:shiro jitsukawa(NIT Fukushima College)

4:10 PM - 4:25 PM

[1C06] Effects of Stress and Dissolved Hydrogen on Grain Boundary Oxidation of Irradiated Stainless Steels

*Takuya Fukumura1, Terumitsu Miura1, Katsuhiko Fujii1, Koji Fukuya1, Yuji Kitsunai2 (1. INSS, 2. NFD)

Keywords:IASCC, Neutron irradiation, Stainless steel, Grain boudary oxidation, Dissolved hydrogen concentration

中性子照射ステンレス鋼の粒界酸化挙動に及ぼす応力と溶存水素濃度（DH）の影響を調べた。応力負荷は粒界酸化を促進させること、DHが2.7～4.1ppmで変化しても粒界酸化に大きく影響しないことが分かった。