Oral presentation

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

[2A15-21] Reactor Pressure Vessel Steels

Thu. Sep 7, 2023 4:10 PM - 6:00 PM Room A (IB Bildg.1F IB013)

Chair:Eiichi Wakai(JAEA)

4:10 PM - 4:25 PM

[2A15] Prediction and Extension of Lifetime of Reactor Pressure Vessel

(1) Irradiation-induced Precipitate G-phase Ni₁₆Si₇Mn₆

*Yoshitaka Matsukawa¹, Daiki Watanabe¹, Sadahiro Tsurekawa¹, Nina Manon Abad¹, Hiroaki Muta², Kenta Yoshida³, Ryuta Kasada³, Masatake Yamaguchi⁴, Hideki Yuya⁵, Minako Endou⁵ (1. Kumamoto Univ., 2. Osaka Univ., 3. Tohoku Univ., 4. JAEA, 5. Chubu Electric Power)

4:25 PM - 4:40 PM

[2A16] Effects of Mn, Ni addition on neutron irradiated RPV model alloys

*Hideo Watanabe¹, Takuya Irie², Masataka Ishii² (1. RIAM, Kyushu Univ.,, 2. IGSES, Kyushu Univ.,)

4:40 PM - 4:55 PM

[2A17] Characterization of Radiation Defects in Low-Cu A533B Steel Irradiated by 5 MeV Electrons Using Three Analytical Techniques: APT, TEM and STEM/EDS

*Katsuhiko Fujii¹, Hitoshi Seto², Koji Fukuya¹, Ryuta Kasada³ (1. INSS, 2. NFD, 3. Tohoku Univ.)

4:55 PM - 5:10 PM

[2A18] Validation of Advanced Prediction Methods for Irradiation Embrittlement Using Machine Learning

*Sakura Nishikawa¹, Liangfan Zhu¹, Yuting Chen¹, Kazunori Morishita¹ (1. Kyoto Univ.)

5:10 PM - 5:25 PM

[2A19] Evaluation of mechanical porperties of weld heat-affected zone in reactor pressure vessel

*Yoosung Ha¹, Masaki Shimodaira¹, Jinya Katsuyama¹ (1. JAEA)

5:25 PM - 5:40 PM

[2A20] Development of high temperature material property equation for base metal and welded joints of reactor pressure vessel steels

*Kenta Shimomura¹, Takuya Yamashita¹, Yuji Nagae¹ (1. JAEA)

5:40 PM - 5:55 PM

[2A21] Probabilistic fracture mechanics analysis using Bayesian nonparametric prediction of irradiation embrittlement

*Hisashi Takamizawa¹, Yinsheng Li¹ (1. JAEA)

Time reserved for Chair (5:55 PM - 6:00 PM)

Session information

[2A15-21] Reactor Pressure Vessel Steels

[2A15] Prediction and Extension of Lifetime of Reactor Pressure Vessel

(1) Irradiation-induced Precipitate G-phase Ni₁₆Si₇Mn₆

[2A16] Effects of Mn, Ni addition on neutron irradiated RPV model alloys

[2A17] Characterization of Radiation Defects in Low-Cu A533B Steel Irradiated by 5 MeV Electrons Using Three Analytical Techniques: APT, TEM and STEM/EDS

[2A18] Validation of Advanced Prediction Methods for Irradiation Embrittlement Using Machine Learning

[2A19] Evaluation of mechanical porperties of weld heat-affected zone in reactor pressure vessel

[2A20] Development of high temperature material property equation for base metal and welded joints of reactor pressure vessel steels

[2A21] Probabilistic fracture mechanics analysis using Bayesian nonparametric prediction of irradiation embrittlement

Authentication

Session information

[2A15-21] Reactor Pressure Vessel Steels

[2A15] Prediction and Extension of Lifetime of Reactor Pressure Vessel

(1) Irradiation-induced Precipitate G-phase Ni16Si7Mn6

[2A16] Effects of Mn, Ni addition on neutron irradiated RPV model alloys

[2A17] Characterization of Radiation Defects in Low-Cu A533B Steel Irradiated by 5 MeV Electrons Using Three Analytical Techniques: APT, TEM and STEM/EDS

[2A18] Validation of Advanced Prediction Methods for Irradiation Embrittlement Using Machine Learning

[2A19] Evaluation of mechanical porperties of weld heat-affected zone in reactor pressure vessel

[2A20] Development of high temperature material property equation for base metal and welded joints of reactor pressure vessel steels

[2A21] Probabilistic fracture mechanics analysis using Bayesian nonparametric prediction of irradiation embrittlement

Authentication

(1) Irradiation-induced Precipitate G-phase Ni₁₆Si₇Mn₆