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Integrity assessment of zircaloy fuel cladding tube experienced transient environmental history of spent fuel pool in Fukushima Dai-ichi Nuclear Power Plant

海水注入等を経験した福島第一原子力発電所使用済燃料プール内ジルカロイ燃料被覆管の健全性評価

関尾 佳弘 ; 山県 一郎 ; 山下 真一郎  ; 佐々木 新治 ; 小川 竜一郎; 益子 真一; 林 長宏; 井上 利彦 ; 井上 賢紀 ; 前田 宏治 

Sekio, Yoshihiro; Yamagata, Ichiro; Yamashita, Shinichiro; Sasaki, Shinji; Ogawa, Ryuichiro; Mashiko, Shinichi; Hayashi, Takehiro; Inoue, Toshihiko; Inoue, Masaki; Maeda, Koji

福島第一原子力発電所(以下、1F)では、東日本大震災発生に伴い、冷却機能の低下した使用済燃料プール(以下、SFP)を含む原子炉建屋内に一定期間のあいだ海水が注入された。本試験では、海水注入を経験した1FSFPに保管されている使用済燃料集合体の長期健全性評価に資するため、1FSFPの水質を模擬した溶液(以下、模擬SFP水)を調整し、この模擬SFP水環境下における使用済ジルカロイ-2燃料被覆管の浸漬試験を実施した。模擬SFP水浸漬前後の表面組織観察を実施した結果、模擬SFP水浸漬による腐食の進行は認められず、強度特性についても引張試験の結果から有意な低下は確認されなかった。

Corrosion and mechanical property tests utilizing spent fuel cladding made of zircaloy-2 were performed as a tentative test of the project for the purpose of simulating an environment at the very early stage after the accident in the SFP of unit 4 in the Fukushima Dai-ichi Nuclear Power Plant. The result of metallurgical investigation after corrosion test showed that no obvious changes in oxide film formed on the outer surface of cladding such as stripping occurred. In addition to that, the ring-tensile test results of samples after corrosion test was obtained and compared with that of samples before corrosion test, indicating that no significant degradation in mechanical property was confirmed. These results would have indicated that integrity of FAs was kept to be high as same as what it was before conducting corrosion test.

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