2023 Annual Meeting

Presentation information

Oral presentation

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

[2F08-10] Dry Storage

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

Chair:Kinya Nakamura(CRIEPI)

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)

Keywords:9×9 fuel cladding, Dry strage, long-term integrity, Tensile test, Recovery of irradiation hardening

9×9燃料(BWR55GWd/t 型)の乾式貯蔵適用性に係る評価の一環として、300 ℃- 360 ℃で最大8000 h熱処理した9×9燃料の使用済燃料被覆管について引張試験を実施した。熱処理温度・時間に伴い強度が低下し延性が増加する傾向を確認した。