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ナトリウム冷却高速炉の炉心崩壊事故における溶融炉心物質の微粒化挙動に関する試験研究; ナトリウム中における溶融酸化物の微粒化試験の結果

Experimental study on fragmentation behavior of molten core material during core disruptive accident for sodium-cooled fast reactors; Results of fragmentation test for molten oxide penetrating into a sodium pool

松場 賢一; 神山 健司; 小西 賢介*; 豊岡 淳一; 佐藤 一憲; Zuev, V.*; Kolodeshnikov, A.*; Yury, V.*

Matsuba, Kenichi; Kamiyama, Kenji; Konishi, Kensuke*; Toyooka, Junichi; Sato, Ikken; Zuev, V.*; Kolodeshnikov, A.*; Yury, V.*

ナトリウム冷却高速炉における炉心崩壊事故の影響緩和方策として、炉心から流出した燃料を微粒化させ、炉容器下部プレナムの受皿で保持することが検討されている。本研究では、10kg程度の溶融アルミナをナトリウム中へ流出させる試験を行い、液柱状の溶融アルミナが微粒化によって崩壊するまでの距離を測定した。

In-vessel retention of molten core fuel with the use of debris trays in a reactor lower plenum is being studied as a mitigation measure against core disruptive accident for sodium-cooled fast reactors. If the molten core fuel is finely fragmented before coming at the debris trays, fuel coolability on the debris trays can be enhanced. In the present study, the length for molten jet break-up due to fragmentation was measured with out-of-pile experiments in which about 10 kg of molten alumina was injected into a sodium pool.

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