| AP1000核电厂蒸汽发生器传热管破裂事故的分析研究 |
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| 引用本文： | 袁明豪,冯雷,周拥辉,于雪良.AP1000核电厂蒸汽发生器传热管破裂事故的分析研究[J].核安全,2009(4):37-41. |
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| 作者姓名： | 袁明豪 冯雷 周拥辉 于雪良 |
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| 作者单位： | [1]苏州热工研究院核安全研究中心,苏州215004 [2]国核工程有限公司,上海200233 |
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| 摘 要： | 使用RELAP程序对AP1000核电厂蒸汽发生器传热管破裂（SGTR）事故进行了分析研究，证明了AP1000核电站在SGTR事故下，不需要操纵员的干预就能依靠非能动安全系统在破损蒸汽发生器满溢之前终止破口流量。重点研究了不同的事故分析假设条件，如厂外电是否可用以及破损蒸汽发生器的释放阀是否打开后卡在开启位置对事故后果的影响。结果表明，即使在对破损蒸汽发生器满溢最不利的假设条件下，AP1000核电站也能避免破损蒸汽发生器满溢，且存在一定的裕量。
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| 关 键 词： | 蒸汽发生器传热管破裂 事故分析 非能动 |
Analysis of Steam Generator Tube Rupture Accident for AP1000 Nuclear Power Plant |
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| YUAN Minghao,FENG Lei,ZHOU Yonghui,YU Xueliang.Analysis of Steam Generator Tube Rupture Accident for AP1000 Nuclear Power Plant[J].Nuclear Safety,2009(4):37-41. |
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| Authors: | YUAN Minghao FENG Lei ZHOU Yonghui YU Xueliang |
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| Affiliation: | 1Nuclear Safety Research Center, Suzhou Nuclear Power Institute, Suzhou 215004, China; 2State Nuclear Power Engineering Corporation Ltd, Shanghai 200233, China) |
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| Abstract: | The analysis of steam generator tube rupture （SGTR） accident for AP1000 nuclear power plant is performed with the system code RELAP. It is demonstrated that under the SGTR accident, AP1000 nuclear power plant is able to stop the break flow prior to overfill of the ruptured steam generator relying on its passive the failure safety systems. Effects of different analysis assumptions, such as availability of offsite power and of the steam generator relief valve in the accident results, are analyzed. It is concluded from the calculation results that AP1000 nuclear power plant can prevent steam generator overfill with significant margin even under the most conservative assumptions. |
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| Keywords: | SGTR accident analysis passive |
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