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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 小坂 一郎川太 徳夫若林 利男
- Publication Date
- 1988-07
- Publication Date (W3CDTF)
- 1988
- Alternative Title
- Analyses of the event of control rod withdrawal under low-power operation in "Fugen".
- Periodical title
- PNC TN9410 88-101
- Target Audience
- 一般
- Note (General)
- 出版タイプ: NA(目的)チェルノブイル事故以降低出力時における原子炉の過渡変化が注目されている。このため「ふげん」の低出力時における制御棒引抜き解析を実施した。(方法)核熱結合一点近似動特性解析コード(EUREKA-2)を用いて、「ふげん」の低出力時での制御棒引抜き解析を行った。(結果)解析から次の事が明らかになった。(1)添+相当事象として観た場合、燃料エンタルピー(非断熱)の最大値は約27Cal/gと小さな値である。(2)スクラム第一信号を無視し、第二信号スクラムとした場合であっても、原子炉は大きなボイド反応度投入前にスクラムされ、過渡変化に与えるボイド反応度の影響は小さい。(結論)解析の結果、設計基準内ではボイド反応度の影響は小さく、反応度投入事象評価指針の判断基準を十分満たす事が確認された。Anticipated reactor transient events under low-power operation have become of interest after the Chernobyl Nuclear Power Plant accident. Therefor, in the present study, the analyses of the event of control rod withdrawal under low-power operation have been carried out for "Fugen", prototype advanced thermal reactor. Analyses have been performed by using EUREKA-2 code, a coupled nuclear thermal hydrodynamic kinetic code. As the result of the analyses, it is confirmed that the effect of coolant void reactivity is almost neglected and that the fuel entarpy is within the limint of established value in the principal guide of reactivity insertion events. In conclusion, there is no matter with control rod withdraw as under low-power operation in design base for "Fugen".
- Source
- /PNC-TN9410-88-101.pdf (fulltext)