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高温ガス炉核的予測精度高度化のための研究開発,4; KUCAを用いたHTTR模擬炉心におけるパワースペクトル解析

R&D to improve accuracy of nuclear prediction for HTGR, 4; Power spectrum analysis for HTTR simulated core in KUCA

左近 敦士*; 中嶋 國弘*; 高橋 和暉*; 芳原 新也*; 佐野 忠史*; 深谷 裕司   ; 橋本 憲吾*

Sakon, Atsushi*; Nakajima, Kunihiro*; Takahashi, Kazuki*; Hohara, Shinya*; Sano, Tadafumi*; Fukaya, Yuji; Hashimoto, Kengo*

京都大学臨界集合体(KUCA)のB架台に構築したHTTR模擬炉心において炉雑音解析による未臨界度測定実験を行った。実験は低出力の臨界状態及びAm-Be中性子源駆動の未臨界状態で実施し、位置の異なる複数の中性子検出器により測定を実施した。実験により取得した中性子検出器時系列データをパワースペクトル法により解析し、体系の即発中性子減衰定数の推定を試みた。

Subcriticality measurement experiment by reactor noise analysis was performed in mock-up core for HTTR configured on B rack of the Kyoto University Critical Assembly (KUCA). The experiments were carried out in low power critical state and in the subcritical state driven by Am-Be neutron source, and the measurements were performed with several neutron detectors at different positions. We analyzed neutron detector time series data acquired by experiment by power spectrum method, and tried to estimate the prompt neutron decay constant of the system.

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