| 核电站非能动余热排出系统误开事故仿真研究 |
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| 引用本文： | 李明岩,彭敏俊,张志俭.核电站非能动余热排出系统误开事故仿真研究[J].应用科技,2009,36(12):52-55. |
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| 作者姓名： | 李明岩 彭敏俊 张志俭 |
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| 作者单位： | 哈尔滨工程大学,核安全与仿真技术国防重点学科实验室,黑龙江,哈尔滨150001 |
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| 摘 要： | 针对非能动余热排出系统在安全壳内的布置方式及运行原理，如果非能动余热排出系统（PRHR：passive residual heat removal）在反应堆正常运行时投入，其效果相当于产生堆芯冷水事故，威胁到堆芯的安全．应用Topmeret、THEATRe建模软件对AP1000非能动余热排出系统误开事故进行仿真研究，分析在此事故下堆芯的安全性．结果表明：在非能动余热排出系统误开的事故中，堆芯的压力、温度及燃料表面温度变化均小于安全域值．
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| 关 键 词： | AP1000 非能动余热排出系统误开 Topmeret THEATRe 核电站 |
Simulation research of the passive residual heat removal system's inadvertent opening accident of a nuclear power plant |
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| LI Ming-yan,PENG Min-jun,ZHANG Zhi-jian.Simulation research of the passive residual heat removal system's inadvertent opening accident of a nuclear power plant[J].Applied Science and Technology,2009,36(12):52-55. |
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| Authors: | LI Ming-yan PENG Min-jun ZHANG Zhi-jian |
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| Institution: | (National Defense Key Subject Laboratory for Nuclear Safety and Simulation Technology, Harbin Engineering University, Harbin 150001, China) |
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| Abstract: | A passive residual heat removal（PRHR） system is used to discharge decay heat of reactor core, which plays a very important role in increasing safety of nuclear power plant. The accident that the PRHR system starts up when a reactor is operating normally is equal to core cold water accident. And this will endanger safety of the reactor core. The modeling software Topmeret and THEATRe are used to carry out simulation on the PRHR of AP1000 and the safety of the core in the accident is analyzed. The simulation results show that core pressure and temperature together with fuel surface temperature change are below safety threshold. |
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| Keywords: | AP1000 Topmeret THEATRe |
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