2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 403-1 Reactor Chemistry, Radiation Chemistry, Corrosion, Water Chemistry,Water Quality Control

[1F08-11] Fuel Cladding Corrosion

Wed. Sep 13, 2017 4:40 PM - 5:45 PM Room F (C214 - C Block)

Chair:Ryuji Nagaishi (JAEA)

5:10 PM - 5:25 PM

[1F10] Evaluation of long-term integrity of the fuel assembly removed from the spent fuel pool

(5)Integrity of fuels during dry storage

*Shinichi Ishioka1,2, Toru Higuchi1,2, Junji Matsunaga3, Masaki Aomi3, Yoshinori Etoh4 (1. IRID, 2. Hitachi-GE Nuclear Energy, 3. Global Nuclear Fuel Japan, 4. Nippon Nuclear Fuel Development)

Keywords:Dry storage, Fuel cladding, Hydride reorientation, Creep

燃料被覆管試験片を用いて水素化物析出挙動確認試験及びクリープ試験を実施し、瓦礫による傷や海水付着およびこれらの重畳影響が燃料健全性に及ぼす影響を評価した。評価の結果、これらの影響は小さいことを確認した。