Oral presentation

[2F08-10] Dry Storage

Tue. Mar 14, 2023 2:45 PM - 3:35 PM Room F (12 Bildg.3F 1232)

Chair:Kinya Nakamura(CRIEPI)

2:45 PM - 3:00 PM

[2F08] Effects of Thermal Annealing on Mechanical Property and Microstructure of BWR Spent Fuel Cladding during Dry Storage

(1) Evaluation of Irradiation Hardening Recovery Behavior from Hardness Measurement

*Masaki Aomi¹, Daichi Yamada², Akihiro Shima², Hideshi TEZUKA², Masashi Shimizu³, Ishioka Shinichi³, Kan Sakamoto⁴, Yusuke Miura⁴, Hiroki Yokoyama⁴ (1. GNF-J, 2. TEPCO HD, 3. HGNE, 4. NFD)

3:00 PM - 3:15 PM

[2F09] Effects of Thermal Annealing on Mechanical Property and Microstructure of BWR Spent Fuel Cladding during Dry Storage

(2) Tensile Properties of Annealed Spent Fuel Cladding

*Yusuke Miura¹, Kan Sakamoto¹, Hiroki Yokoyama¹, Masaki Aomi², Masashi Shimizu³, Shinichi Ishioka³, Daichi Yamada⁴, Akihiro Shima⁴, Hideshi Tezuka⁴ (1. NFD, 2. GNF-J, 3. HGNE, 4. TEPCO HD)

3:15 PM - 3:30 PM

[2F10] Effect of Thermal Annealing on Mechanical Property and Microstructure of BWR Spent Fuel Cladding during Dry Storage

(3) Evaluation of Microstructure of Annealed Spent Fuel Cladding

*Hiroki Yokoyama¹, Kan Sakamoto¹, Yusuke Miura¹, Masaki Aomi², Masashi Shimizu³, Shinichi Ishioka³, Daichi Yamada⁴, Akihiro Shima⁴, Hideshi Tezuka⁴ (1. NFD, 2. GNF-J, 3. HGNE, 4. TEPCO HD)

Time reserved for Chair （3:30 PM - 3:35 PM）

Oral presentation

[2F11-15] Next Generation Fuel, Accident Tolerant Fuel

Tue. Mar 14, 2023 3:35 PM - 5:00 PM Room F (12 Bildg.3F 1232)

Chair:Shun Hirooka(JAEA)

3:35 PM - 3:50 PM

[2F11] MOX fuel technologies for next-generation nuclear reactors

(1) Evaluation of electronic defect contribution in heat capacity and thermal conductivity

*Masato Kato¹, Shun Hirooka¹, Masashi Watanabe¹, Romain Vauchy¹, Takumi Oki¹ (1. JAEA)

3:50 PM - 4:05 PM

[2F12] MOX fuel technologies for next-generation nuclear reactors

(2) Study of thermal conductivity and irradiation behavior for MOX fuel

*Takumi Oki¹, Masato Kato¹, Yoshihisa Ikusawa¹, Shun Hirooka¹ (1. JAEA)

4:05 PM - 4:20 PM

[2F13] Technological development of the particle size adjustment of recycle powder

(8) Sintered density control with dry recovered powder and microstructure evaluation

*Tomoomi Segawa¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Kazuya Yamamoto¹, Takayoshi Makino¹, Kazuyuki Okumura¹ (1. JAEA)

4:20 PM - 4:35 PM

[2F14] Sintering behavior of dry-recycled MOX powder with various particle size distribution

*Kohei Hayashizaki¹, Shun Hirooka¹, Takeo Sunaoshi², Shinya Nakamichi¹, Tatsutoshi Murakami¹ (1. JAEA, 2. Inspection Development)

4:35 PM - 4:50 PM

[2F15] Behavior of Chromium-coated Zirconium alloy fuel rods in simulated beyond design basis accident

*Kinya Nakamura¹, Kenta Inagaki¹, Juri Stuckert², Martin Ševeček³ (1. CRIEPI, 2. KIT, 3. CTU)

Time reserved for Chair （4:50 PM - 5:00 PM）

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior