Oral presentation

[3F01-04] Irradiation Effects

Wed. Mar 15, 2023 9:30 AM - 10:40 AM Room F (12 Bildg.3F 1232)

Chair:Kenichi Fukumoto(The University of Fukui)

9:30 AM - 9:45 AM

[3F01] Evaluation of Electron Beam Irradiation Behavior for Polyethylene

*Yukiko Furuhashi¹, Yuta Mashiko¹, Tadashi Yamane¹ (1. TEPCO HD)

9:45 AM - 10:00 AM

[3F02] Changes in strength of PNC-FMS for wrapper tube of fast reactor by long-term thermal aging

*Koji Fujita¹, Yuta Shizukawa¹, Takashi Tanno¹, Yasuhide Yano¹ (1. Japan Atomic Energy Agency)

10:00 AM - 10:15 AM

[3F03] Formation mechanism of point defect clusters in collision cascades: large-scale molecular dynamics simulations

*Yuting Chen¹, kazunori morishita¹ (1. Kyoto Univ.)

10:15 AM - 10:30 AM

[3F04] Statistical assessment of athermal point defects in iron during neutron irradiation

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

Time reserved for Chair （10:30 AM - 10:40 AM）

Oral presentation

[3F05-09] Light Water Reactor Materials

Wed. Mar 15, 2023 10:40 AM - 11:55 AM Room F (12 Bildg.3F 1232)

Chair:Kazunori Morishita(Kyoto University)

10:40 AM - 10:55 AM

[3F05] Study on the local mechanical properties at the interface of RPV cladding

Takashi Noro¹, *Ryuta KASADA Kasada¹, Hao Yu¹, Diancheng Geng¹, Sosuke Kondo¹, Hideki Yuya², Minako Endo² (1. Tohoku Univ., 2. Chubu Electric Power)

10:55 AM - 11:10 AM

[3F06] Effect of Ni addition on dislocation loop formation in Fe-Mn alloys

*Yuta Ishida¹, Ken-Ichi Fukumoto¹, Fujii Katsuhiko² (1. UNIVERSITY OF FUKUI, 2. Institute of Nuclear Safety System, Inc.)

11:10 AM - 11:25 AM

[3F07] Evaluation of irradiation embrittlement of a harvested reactor pressure vessel material from a domestic PWR plant

(1) Investigation of solute atom cluster formation

*Toru Oumaya¹, Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹ (1. Institute of Nuclear Safety System, Incorporated)

11:25 AM - 11:40 AM

[3F08] Evaluation of irradiation embrittlement of a harvested reactor pressure vessel material from a domestic PWR plant

(2) Investigation of hardness and dislocation loop formation

*Terumitsu Miura¹, Toru Oumaya¹, Katsuhiko Fujii¹, Koji Fukuya¹ (1. Institute of Nuclear Safety System)

11:40 AM - 11:55 AM

[3F09] Correlation between crack growth and corrosion behavior of cobalt-based alloy in simulated PWR primary water

*Takuyo Yamada¹, Takahiro Sasaoka², Takumi Terachi², Yoshiari Kaneshima¹, Kohei Kokutani¹, Koji Arioka¹ (1. INSS, 2. KEPCO)

Oral presentation

[3F10-11] Zirconium Alloys

Wed. Mar 15, 2023 2:45 PM - 3:15 PM Room F (12 Bildg.3F 1232)

Chair:Masafumi Nakatsuka(Zirco Technology)

2:45 PM - 3:00 PM

[3F10] Oxide Film Formation Behavior of Ion-Irradiated Zirconium Alloy

*Katsuhito Takahashi¹, Yun Wang¹, Yasuhisa Aono¹, Takashi Mutaguchi², Shun Shimabukuro², Hideo Watanabe² (1. Hitachi, 2. Kyushu Univ.)

3:00 PM - 3:15 PM

[3F11] Evaluation of irradiation induced hardness and microstructure of Zry-2 under applied stress (2)

*Luwei Xue¹, Hideo Watanabe¹ (1. Kyushu Univ.)

Oral presentation

[3F12-14] Ceramics

Wed. Mar 15, 2023 3:15 PM - 4:00 PM Room F (12 Bildg.3F 1232)

Chair:Ryuta KASADA Kasada(Tohoku Univ.)

3:15 PM - 3:30 PM

[3F12] Effect of high temperature ion irradiation on swelling and microstructure of Liquid Phase Sintering SiC

*Yansong Zhong¹, Baopu Wang¹, Yina Du¹, Kanjiro Kawasaki¹, Fujio Shinoda¹, Yasunori Hayashi¹, Tatsuya Hinoki¹ (1. Kyoto Univ.)

3:30 PM - 3:45 PM

[3F13] Effects of Irradiation Temperature and Fluence on Mechanical Properties and Surface Residual Stress of SiC

*Baopu WANG¹, Yansong ZHONG¹, Yina DU¹, Kanjiro KAWASAKI¹, Fujio SHINODA¹, Yasunori HAYASHI¹, Tatsuya HINOKI¹ (1. Kyoto Univ.)

3:45 PM - 4:00 PM

[3F14] X-ray Absorption Spectroscopy Study of Cationic Disorder in Spinel Structure Induced on Swift Heavy Ion Irradiations

*Satoru Yoshioka¹, Tomokazu Yamamoto¹, Kazuhiro Yasuda¹, Syo Matsumua², Eiichi Kobayashi³, Koji Okudaira⁴, Norito Ishikawa⁵ (1. Kyushu Univ., 2. NIT Kurume college, 3. SAGA Light Source, 4. Chiba Univ., 5. JAEA)

Oral presentation

[3F15-16] Non-destructive inspection

Wed. Mar 15, 2023 4:00 PM - 4:30 PM Room F (12 Bildg.3F 1232)

Chair:Katsuhito Takahashi(Hitachi)

4:00 PM - 4:15 PM

[3F15] Development of visual inspection technology of pellets using machine learning

(2)Demonstration experiment using MOX pellets and consideration for introduction to production line

*Kenta Goto¹, Shun Hirooka¹, Yuta Horii¹, Shinya Nakamichi¹, Tatsutoshi Murakami¹, Kimikazu Shibanuma¹, Takanori Ono¹, Kazuya Yamamoto¹, Nobuhiro Hatanaka¹, Kazuyuki Okumura¹ (1. JAEA)

4:15 PM - 4:30 PM

[3F16] Preliminary experiments for the development of fuel debris sorting technology by hammering method

*Masafumi Nakatsuka¹, Yoichi Endo², Toru Higuchi², Masaya Kumagai³, Ken Kurosaki³ (1. Zirco Technology, 2. NFD, 3. Kyoto Univ.)

Sessions

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

[3F01-04] Irradiation Effects

[3F01] Evaluation of Electron Beam Irradiation Behavior for Polyethylene

[3F02] Changes in strength of PNC-FMS for wrapper tube of fast reactor by long-term thermal aging

[3F03] Formation mechanism of point defect clusters in collision cascades: large-scale molecular dynamics simulations

[3F04] Statistical assessment of athermal point defects in iron during neutron irradiation

[3F05-09] Light Water Reactor Materials

[3F05] Study on the local mechanical properties at the interface of RPV cladding

[3F06] Effect of Ni addition on dislocation loop formation in Fe-Mn alloys

[3F07] Evaluation of irradiation embrittlement of a harvested reactor pressure vessel material from a domestic PWR plant

(1) Investigation of solute atom cluster formation

[3F08] Evaluation of irradiation embrittlement of a harvested reactor pressure vessel material from a domestic PWR plant

(2) Investigation of hardness and dislocation loop formation

[3F09] Correlation between crack growth and corrosion behavior of cobalt-based alloy in simulated PWR primary water

[3F10-11] Zirconium Alloys

[3F10] Oxide Film Formation Behavior of Ion-Irradiated Zirconium Alloy

[3F11] Evaluation of irradiation induced hardness and microstructure of Zry-2 under applied stress (2)

[3F12-14] Ceramics

[3F12] Effect of high temperature ion irradiation on swelling and microstructure of Liquid Phase Sintering SiC

[3F13] Effects of Irradiation Temperature and Fluence on Mechanical Properties and Surface Residual Stress of SiC

[3F14] X-ray Absorption Spectroscopy Study of Cationic Disorder in Spinel Structure Induced on Swift Heavy Ion Irradiations

[3F15-16] Non-destructive inspection

[3F15] Development of visual inspection technology of pellets using machine learning

(2)Demonstration experiment using MOX pellets and consideration for introduction to production line

[3F16] Preliminary experiments for the development of fuel debris sorting technology by hammering method

Authentication