| 主给水管断裂事故敏感性研究 |
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| 引用本文： | 郑文祥,居怀明.主给水管断裂事故敏感性研究[J].原子能科学技术,1989,23(5):23-28. |
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| 作者姓名： | 郑文祥 居怀明 |
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| 作者单位： | 清华大学核能技术研究所 北京
(郑文祥，居怀明)，清华大学核能技术研究所 北京(李国伟) |
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| 摘 要： | 文章利用RETRAN-02/MOD 002程序对秦山核电厂主给水管断裂事故进行了敏感性分析研究。着重研究了蒸汽发生器及其传热模型、破口大小、停堆时间和辅助给水进入蒸汽发生器的时间对瞬变过程的影响,并分析了主给水管断裂事故的示例工况。文章给出了这些研究的主要结果。
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| 关 键 词： | 核电厂 给水管 断裂 事故 |
SENSITIVITY STUDIES OF THE MAIN FEEDWATER LINE RUPTURE |
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| ZHENG WENXIANG,JU HUAIMING,LI GUOWEI Institute of Nuclear Energy Technology,Tsinghua University,Beijing.SENSITIVITY STUDIES OF THE MAIN FEEDWATER LINE RUPTURE[J].Atomic Energy Science and Technology,1989,23(5):23-28. |
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| Authors: | ZHENG WENXIANG JU HUAIMING LI GUOWEI Institute of Nuclear Energy Technology Tsinghua University Beijing |
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| Abstract: | The sensitivity studies of a main feedwater line rupture for Qinshan nuclearpower plant are performed with RETRAN-02/MOD 002. The studies place emph-asis on the primary to secondary heat transfer models of steam generator, breaksizes, credit taken for functioning of reactor trip and timing of auxiliary feedwatersupply to intact steam generator, A typical case of the main feedline rupturis analysed. This paper presents the main results of these studies. |
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| Keywords: | Nuclear power plant Steam generator Feedwater line rupture Sensitivity study |
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