一般講演

[G] Nuclear Materials

Thu. Mar 9, 2023 9:00 AM - 11:45 AM Rm. K (Rm.1311,1st Flr.,Buld.No.13)

座長:外山健(東北大学)、藪内聖皓(京都大学)

※表示の講演時間には質疑応答時間も含みます。
（質疑応答時間5分、基調講演と招待講演は5～10分）

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9:00 AM - 9:15 AM

[259] Electron microscopy of the interaction between defects and domain walls in iron alloys ②

*Junichi Hirabayashi¹, Toshiyuki Fujita¹, Fumihisa Kano¹, Takehito Seki², Naoya Shibata² (1. Toshiba Energy Systems & Solutions Corp., 2. The University of Tokyo)

9:15 AM - 9:30 AM

[260] Application of APT Analysis to Measurement of Grain Boundary Segregation of Light Elements in Steels

*Katsuhiko FUJII¹, Koji FUKUYA¹ (1. INSS)

9:30 AM - 9:45 AM

[261] Simulation for helium in Fe-vacancy and copper precipitation

*Kazuhito OOSAWA¹, Qiu XU², Hideo WATANABE¹ (1. RIAM Kyushu Univ., 2. IIRNS Kyoto Univ.)

9:45 AM - 10:00 AM

[262] Improved irradiation resistance of Cr-Fe alloy for ATF application

*Lijuan Cui¹, Huilong Yang¹, Yufeng Du², Sho Kano¹, Hiroaki Abe¹ (1. UTokyo、2. Tohoku university)

10:00 AM - 10:15 AM

[263] Behavior of point defects under spot-ion irradiation in semiconductor materials

*Naoto Oishi¹, Takahiro Ueda¹, Noriko Nitta¹ (1. Kochi University of Technology)

break （10:15 AM - 10:30 AM）

10:30 AM - 10:45 AM

[264] The microstructure and formation process of the Cr-Zry4 interface for accident tolerant fuel application

*LI BO¹, Yang Huilong², Cui Lijuan¹, Holmes Reuben¹, KANO Sho¹, Abe Hiroaki¹ (1. Graduate School of Engineering, The University of Tokyo、2. School of Nuclear Science and Engineering, Shanghai Jiao Tong University)

10:45 AM - 11:00 AM

[265] On the tensile behaviors of the Cr-Zircaloy bilayer fabricated by diffusion bonding

*Ziqi Wei¹, Huilong Yang², Bo Li¹, Lijuan Cui¹, Sho Kano¹, Hiroaki Abe¹ (1. Graduate School of Engineering, The University of Tokyo、2. School of Nuclear Science and Engineering, Shanghai Jiao Tong University)

11:00 AM - 11:15 AM

[266] Thermal-hydraulic and oxidation corrosion coupled simulation of lead-based fast reactors

*Yan ZHANG^1,2, Chenglong Wang¹, Dalin Zhang¹, Wenxi Tian¹, Guanghui Su¹, Suizheng Qiu¹, Hiroaki Abe² (1. School of Nuclear Science and Technology, Xi'an Jiaotong University、2. Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo)

11:15 AM - 11:30 AM

[267] Development of cladding technology for FeCrAl alloys coexisting with liquid metal

*Naoko OONO¹, Taro NAGANO¹ (1. Yokohama National Univ.)

11:30 AM - 11:45 AM

[268] Developing the determination method of the elastic stiffness coefficients
of the intermetallic compound G-phase by experiments

*Yoshitaka MATSUKAWA¹, Yuichi Araki¹, Sadahiro Tsurekawa¹, Diancheng Geng², Koichi Harata², Ryuta Kasada², Hiroaki Muta³, Masatake Yamaguchi⁴ (1. Kumamoto Univ., 2. Tohoku Univ., 3. Osaka Univ., 4. Japan Atomic Energy Agency)

一般講演

[G] Nuclear Materials

Thu. Mar 9, 2023 1:00 PM - 4:00 PM Rm. K (Rm.1311,1st Flr.,Buld.No.13)

Chair:Naoko Hori Oono

※表示の講演時間には質疑応答時間も含みます。
（質疑応答時間5分、基調講演と招待講演は5～10分）

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1:00 PM - 1:15 PM

[269] The radiation-induced amorphization of second-phase particles in F82H steel (3rd report)

*Sho KANO¹, Hiroaki Abe¹ (1. U-Tokyo)

1:15 PM - 1:30 PM

[270] Sink effect of grain boundaries on radiation-induced point defects in F82H

*Naoyuki HASHIMOTO¹, Hiroshi OKA¹, Yoshyuki WATANABE², Takashi NOZAWA² (1. Faculty of Engineering, Hokkaido Univ., 2. QST)

1:30 PM - 1:45 PM

[271] Evolution of the F82H/Cr interface during diffusion bonding above and below Ac₁ temperature

*Reuben HOLMES¹, Li BO¹, Lijuan CUI¹, Sho KANO¹, Huilong YANG², Hiroaki ABE¹ (1. The University of Tokyo、2. Shanghai Jiao Tong University)

1:45 PM - 2:00 PM

[272] Applicability evaluation of Larson-Miller parameter (LMP)-Life fraction rule to high-temperature strength of 9Cr-ODS steels

*Takeshi MIYAZAWA¹, Takashi Tanno¹, Yuuya Imagawa¹, Ryuuta Hashidate¹, Yasuhide Yano¹, Satoshi Ohtsuka¹, Takeji Kaito¹, Masatoshi Mitsuhara², Hideharu Nakashima², Masato Ohnuma³, Takeshi Toyama⁴ (1. JAEA, 2. Kyushu Univ., 3. Hokkaido Univ., 4. Tohoku Univ.)

2:00 PM - 2:15 PM

[273] The Stability of Nano-Oxides in ODS Steels under Ion Irradiation

*WANG ZIDENG¹、YANG HUILONG², LIJUAN CUI¹, SHEN JINGJIE³, KANO SHO¹, ABE HIROAKI¹ (1.Graduate School of Engineering, the University of Tokyo, 2.School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 3.National Institute for Fusion Science)

2:15 PM - 2:30 PM

[274] Development of high entropy alloys with reduced void swelling for high burnup core materials

*Hiroshi OKA¹, Takumu Niino², Kazuya Ono³, Naoyuki Hashimoto¹, Shigehito Isobe¹ (1. Faculty of Engineering, Hokkaido Univ., 2. Graduate School of Engineering, Hokkaido Univ., 3. School of Engineering, Hokkaido Univ.)

break （2:30 PM - 2:45 PM）

2:45 PM - 3:00 PM

[275] Changes of hardness and Cr precipitates in Cu-Cr-Zr alloy aged at 480 ℃

*Takeshi TOYAMA¹, Hughes J², Gorley M³, Inoue K¹, Nagai Y¹, Jimenez-Melero E² (1. IMR, Tohoku U, 2. The Univ. of Manchester, 3. UK Atomic Energy Authority)

3:00 PM - 3:15 PM

[276] Change in hardness in Fe-ion-irradiated single-crystal tungsten by hydrogen charging

Kentaro UENO¹, *Koichi SATO¹, Dingcheng GENG², Ryuta KASADA², Kiyohiro YABUUCHI³, Qiu XU⁴, Masahiko HATAKEYAMA⁵ (1. Kagoshima Univ., 2. Inst. Mater. Res., Tohoku Univ., 3. Inst. Adv. Energy, Kyoto Univ., 4. Inst. Integr. Radiat. Nucl. Sci., Kyoto Univ., 5. Univ. of Toyama)

3:15 PM - 3:30 PM

[277] Microstructure Analysis of Neutron Irradiated Pure W and W alloys with Thermal Neutron Shield

*Akira HASEGAWA¹, Kenta YOSHIDA¹ (1. IMR, Tohoku University)

3:30 PM - 3:45 PM

[278] In-situ microstructural evolution of Cr0.8FeMnNi and 316L under heavy ion irradiation with He implantation

*Mengke NIU¹, Naoyuki HASHIMOTO², Hiroshi OKA², Shigehito ISOBE² (1. Graduate School of Engineering, Hokkaido University, 2. Faculty of Engineering, Hokkaido University)

3:45 PM - 4:00 PM

[279] Effect of Al content on irradiation hardening and defect microstructure of Fe/He ion irradiated Al_xCrCuFeNi₂ high entropy alloys at 500°C

*Peng BI¹, Naoyuki HASHIMOTO², Hiroshi OKA², Shigehito ISOBE² (1. Graduate School of Engineering, Hokkaido Univ., 2. Faculty of Engineering, Hokkaido Univ.)

Sessions

10. Energy and Related Materials » Nuclear Materials

[G] Nuclear Materials

[259] Electron microscopy of the interaction between defects and domain walls in iron alloys ②

[260] Application of APT Analysis to Measurement of Grain Boundary Segregation of Light Elements in Steels

[261] Simulation for helium in Fe-vacancy and copper precipitation

[262] Improved irradiation resistance of Cr-Fe alloy for ATF application

[263] Behavior of point defects under spot-ion irradiation in semiconductor materials

[264] The microstructure and formation process of the Cr-Zry4 interface for accident tolerant fuel application

[265] On the tensile behaviors of the Cr-Zircaloy bilayer fabricated by diffusion bonding

[266] Thermal-hydraulic and oxidation corrosion coupled simulation of lead-based fast reactors

[267] Development of cladding technology for FeCrAl alloys coexisting with liquid metal

[268] Developing the determination method of the elastic stiffness coefficients
of the intermetallic compound G-phase by experiments

[G] Nuclear Materials

[269] The radiation-induced amorphization of second-phase particles in F82H steel (3rd report)

[270] Sink effect of grain boundaries on radiation-induced point defects in F82H

[271] Evolution of the F82H/Cr interface during diffusion bonding above and below Ac₁ temperature

[272] Applicability evaluation of Larson-Miller parameter (LMP)-Life fraction rule to high-temperature strength of 9Cr-ODS steels

[273] The Stability of Nano-Oxides in ODS Steels under Ion Irradiation

[274] Development of high entropy alloys with reduced void swelling for high burnup core materials

[275] Changes of hardness and Cr precipitates in Cu-Cr-Zr alloy aged at 480 ℃

[276] Change in hardness in Fe-ion-irradiated single-crystal tungsten by hydrogen charging

[277] Microstructure Analysis of Neutron Irradiated Pure W and W alloys with Thermal Neutron Shield

[278] In-situ microstructural evolution of Cr0.8FeMnNi and 316L under heavy ion irradiation with He implantation

[279] Effect of Al content on irradiation hardening and defect microstructure of Fe/He ion irradiated Al_xCrCuFeNi₂ high entropy alloys at 500°C

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