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高速炉格納容器バウンダリの耐圧強度評価手法の開発,2; 中高面に圧力を受ける鏡板の限界圧力試験

Development of evaluation methods of ultimate behavior for fast reactor containment vessel boundary, 2; Burst pressure test of head pleat subject to convex side pressure

矢田 浩基; 安藤 勝訓; 月森 和之; 一宮 正和*; 安濃田 良成*

Yada, Hiroki; Ando, Masanori; Tsukimori, Kazuyuki; Ichimiya, Masakazu*; Anoda, Yoshinari*

高速炉の重大事故対策に関して、原子炉格納容器は1次冷却材バウンダリが破損した際に、放射性物質を留める重要な機器であるため事故時の放射性物質の拡散防止の観点から、その適切な機能維持が求められる。本稿では、高速炉の原子炉格納容器バウンダリのなかで、1次冷却材と2次冷却材とのバウンダリを構成する中間熱交換器2次側下部鏡について、1次冷却材圧力が上昇した際の破損様式の検証と限界圧力の評価法の開発を目的とした試験および解析を実施した。

Containment vessel is an important structure to prevent a significant and sudden radioactive release under the severe accidents. In case of the severe accidents, the pressure generated in the containment vessel is supposed to exceed the maximum design pressure. The required function of the containment vessel as radiological confinement should be enhanced, as far as reasonably achievable. To clarify the progress of events under the severe accidents and design the severe accident countermeasure equipment, it is necessary to evaluate the pressure toughness of containment vessel boundary adequately. The containment vessel of fast reactor is composed of the various structures. The head plate that is primary and secondary coolant boundary in intermediate heat exchanger has important role when the progress of the events under the severe accidents is considered. Therefore, in order to develop the evaluation method of the pressure toughness under the severe accidents, the burst pressure test of the head plate subjected to convex side pressure was performed, and burst pressure test was evaluated by FEM analysis.

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