検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

再処理用材料の腐食による劣化とその機構,4; ホット環境におけるジルコニウム製機器の環境助長割れ確認試験

Corrosion mechanism of component materials used in nuclear fuel reprocessing plant, 4; Confirmation of environment assisted cracking of zirconium by hot laboratory tests

沼田 正美; 加藤 千明; 本岡 隆文; 遠藤 慎也; 喜多川 勇; 木崎 實; 山本 正弘; 木内 清

Numata, Masami; Kato, Chiaki; Motooka, Takafumi; Endo, Shinya; Kitagawa, Isamu; Kizaki, Minoru; Yamamoto, Masahiro; Kiuchi, Kiyoshi

核燃料再処理施設の機器のうち、燃料溶解槽等のジルコニウム製機器について、使用済み燃料溶解液における環境助長割れに関する検討を行い、コールド模擬液の妥当性を検証した。また、実機に近い環境を模擬するためにCo$$^{60}$$を用いた$$gamma$$線照射を用いて放射線の影響を検討した。その結果、コールド模擬液の妥当性を確認し、放射線による環境助長割れの加速が生じないことを明らかにした。

We estimated environment assisted cracking of zirconium such as the unclear fuel dissolver in spent unclear fuel solution and considered the cold simulated solution with substituted similar oxidization ions for trans-uranium (TRU) and fission products (FP) and difference between the cold simulated solution and the hot spent unclear fuel. In addition, we considered radiation effect of $$gamma$$ ray under irradiation of cobalt-60 to simulate closely the dissolver condition. In this report, we confirmed that the cold simulated solution is appropriate solution to substitute for the spent nuclear fuel solution and radiation of $$gamma$$ ray doesn't accelerate environment assisted cracking of zirconium.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.