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タンク型SFRの炉内配管破損の解析

Analyses of pump/diagrid link rupture in pool type sodium-cooled fast reactor

小野田 雄一; 内田 昌人*; 時崎 美奈子*; 岡崎 仁*

Onoda, Yuichi; Uchita, Masato*; Tokizaki, Minako*; Okazaki, Hitoshi*

タンク型SFRの設計基準事象の候補である炉内配管破損を対象に安全解析を行い、安全保護系信号の充足性について確認した。初期出力状態(定格,部分出力)、反応度フィードバックの不確かさ等、影響が大きいと考えられるパラメータについて複数の感度解析を行った結果、開発ターゲットとして暫定している安全保護系信号の目標(炉内配管破損に対し複数信号確保)を満足できる見通しを得た

The safety analyses were carried out to confirm the sufficiency of the function of the plant protection system against the pump/diagrid link rupture, which is a candidate of the design basis event in pool type SFR. Sensitivity has been studied for the parameters which are thought significantly to affect the detection of the pump/diagrid link rupture, such as initial reactor power (at rated and 30% power operation), reactivity feedbacks and so forth. The sufficiency of the function was confirmed by the analysis results that at least two signals are transmitted for the detection of the pump/diagrid link rupture, which is the development target of the plant protection system in pool type SFR.

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