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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 大洗研福島技術開発特別チーム福島燃料材料試験部
- Publication Date
- 2014-06
- Publication Date (W3CDTF)
- 2014
- Alternative Title
- Long term integrity of reactor pressure vessel and primary containment vessel after the severe accidents in Fukushima Daiichi Nuclear Power Station; Leaching property of spent oxide fuel segment and corrosion property of a carbon steel under artificial seawater immersion
- Periodical title
- JAEA-Research 2014-007
- Target Audience
- 一般
- Note (General)
- 出版タイプ： NA福島第一原子力発電所1$\sim$3号機の格納容器(PCV)、原子炉圧力容器、ペデスタル等の主要構造物は、炉心溶融事象と応急措置的な冷却のために注入された海水の影響により、熱的・化学的・機械的に厳しい環境に曝されている。今後のPCV内の継続的冷却と燃料デブリ取出し作業時の水張りを展望すると、主要構造物の全部あるいは一部は長期にわたり水浸漬状態になると予想される。炉心に注入された冷却水はデブリ等と接触して成分を溶解し、同時に滞留している水と混合して汚染水になる。そこで、50$^{\circ}$C程度の低温期におけるデブリ等から汚染水への核分裂生成物の移行に着目した。「ふげん」照射済燃料を使用した浸漬試験を行い、核分裂生成物、アクチニド等の溶出特性を評価した。PCVはその内側に存在する核分裂生成物を包蔵する重要な障壁であり、汚染水との接触による腐食特性が注目される。汚染水を想定した人工海水を調整し、50$^{\circ}$Cにおける浸漬試験と電気化学試験により、PCV構成材料である炭素鋼の腐食特性を評価した。評価にあたっては、影響因子として溶存する核分裂生成物(特に、セシウム)と放射線の化学的効果を考慮した。Primary containment vessel (PCV), reactor pressure vessel and pedestal in Fukushima Daiichi Nuclear Power Station units 1 through 3 have been exposed to severe thermal, chemical and mechanical conditions due to core meltdown events and seawater injections for emergent core cooling. These components will be immersed in diluted seawater with dissolved fission products under irradiation until the end of debris removal. Fresh water injected into the cores contacts with debris to cool, dissolutes or erodes their constituents, mixed with retained water, and becomes "accumulated water" with radioactive nuclides. We have focused the leaching of fission products into the accumulated water under lower temperature (323 K). FUGEN spent oxide fuel segments were immersed to determine the leaching factor of fission product and actinide elements. Since PCV made from carbon steel is one of the most important boundaries to prevent from fission products release, corrosion behavior has been paid attention to evaluate their integrity. Carbon steel specimens were immersion- and electrochemical-tested in diluted seawater with simulants of the accumulated water at 323 K. in order to evaluate the effect of fission products in particular cesium and radiation.
- Source
- /JAEA-Research-2014-007.pdf （fulltext）