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High-temperature behavior of accident-tolerant control rods clad with Zr alloy during BDBA and SA leading to reaction with molten fuel

溶融燃料との反応に至る過酷事故時の事故耐性制御棒被覆管とジルコニウム合金の高温挙動

中村 勤也*; 太田 宏一*; 高野 公秀 

Nakamura, Kinya*; Ota, Hirokazu*; Takano, Masahide

電力中央研究所では、軽水炉の事故耐性向上のため、燃料と並行して制御棒の開発も必要であることを2013年から指摘しており、事故耐性制御棒の開発を進めてきた。これは事故耐性のみならず、使用済制御棒を減らすなど経済性向上も期待されるものである。制御棒と燃料棒ともにZr合金被覆管を使用することを想定し、新型の中性子吸収材であるEu-Hf系酸化物固溶体とZr合金の高温反応挙動を設計基準事故を超える条件下で実験により調べた結果、少なくとも1700$$^{circ}$$Cまでは健全性を保っており、従来の制御棒より事故耐性が優れることを確認した。さらに、上記中性子吸収材と溶融燃料成分である(U,Zr)O$$_{2}$$の高温反応挙動を過酷事故条件である2200から2600$$^{circ}$$Cの範囲で実験により調べた結果、相互溶解性が良好で均質な酸化物固溶体を形成することを確認した。事故後の再臨界の危険性が抑制されることから、希土類-Zr系または希土類-Hf系酸化物固溶体とZr合金被覆からなる新型の事故耐性制御棒の概念が優れていることを明らかにした。

CRIEPI has pointed out since 2013 that control rods (CRs) and fuel rods should be developed in parallel both to enhance accident tolerance of light water reactors. CRIEPI has been developing accident-tolerant control rod (ATCR) that can be also expected to improve economic efficiency and reduce the number of spent CRs. Assuming the application of coated Zr alloy to fuel and CR cladding, high temperature integrity test of a novel neutron absorber Eu$$_{2}$$O$$_{3}$$-50mol% HfO$$_{2}$$ clad with Zr alloy was carried out under the beyond DBA condition. The results showed that the ATCR concept clad with Zr alloy cladding had good integrity without deformation to at least 1700$$^{circ}$$C. To confirm the miscibility of the novel neutron absorber and the molten fuel under severe accident (SA) conditions, the reaction test between the absorber pellet and (U,Zr)O$$_{2}$$ pellet as molten fuel simulant was carried out in Ar atmosphere in the temperature range of 2200 to 2600$$^{circ}$$C. it was clarified that the Zr- based alloy-clad ATCR concept such as rare earth (RE)-Zr mixed oxide or RE-Hf mixed oxide is highly compatible with oxidic melt containing U and is likely to significantly reduce the risk of recriticality during and after SA.

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