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高速炉自然循環時炉心内熱流動現象に対するプラント動特性解析コードの妥当性確認

Validation of plant dynamics analysis code for fast reactor core thermal hydraulics under natural circulation conditions

浜瀬 枝里菜 ; 堂田 哲広 ; 鍋島 邦彦 ; 小野 綾子 ; 大島 宏之

Hamase, Erina; Doda, Norihiro; Nabeshima, Kunihiko; Ono, Ayako; Ohshima, Hiroyuki

高速増殖炉の自然循環時炉心内では浮力や熱伝導の効果が卓越し、燃料集合体間/内流量再配分、集合体間熱移行、集合体間ギャップ部流れといった炉内熱流動現象が重要になる。日本原子力研究開発機構では、自然循環崩壊熱除去時の炉心最高温度を精度よく評価するため、これらの現象を考慮できる全炉心熱流動モデルを組み込んだプラント動特性解析コードSuper-COPDの整備を行っている。本報では、7本の模擬燃料集合体から成るナトリウム試験装置を用いた自然循環試験の解析を実施し、集合体間熱移行現象に関する本モデルの妥当性を確認した。

Under natural circulation decay heat removal conditions, three characteristic phenomena; flow redistribution in the core as well as in the fuel subassemblies, inter-subassembly heat transfer and gap flow between wrapper tubes of fuel subassemblies are important for assessing the temperature distribution in the core. In order to improve the prediction accuracy, a whole core model which can consider these three phenomena has been incorporated into the plant dynamics analysis code Super-COPD. In this study, analyses of two kinds of sodium experiments were performed to validate Super-COPD with the whole core model, which were focusing on inter-subassembly heat transfer phenomena.

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