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)

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)

Keywords:9x9 fuel cladding, dry storage, long-term integrity, hardness measurement, irradiation hardening recovery

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、商用炉で5サイクル照射された9×9燃料被覆管試験片を270 ℃ - 360 ℃で最大8000 hまで加熱し、その後微小ビッカース硬さ測定を実施した。硬さ変化と熱処理条件の関係から、照射硬化回復挙動を評価した。