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核电站非能动余热排出系统误开事故仿真研究 被引量:2

Simulation research of the passive residual heat removal system’s inadvertent opening accident of a nuclear power plant
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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:pas-sive 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. 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.
出处 《应用科技》 CAS 2009年第12期52-55,共4页 Applied Science and Technology
关键词 AP1000 非能动余热排出系统误开 Topmeret THEATRE 核电站 AP1000 passive residual heat removal system's inadvertent opening Topmeret THEATRe naeher Power Plant
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参考文献5

  • 1沈瑾,江光明,唐钢.AP1000非能动安全系统初步应用研究[J].国外核动力,2006,27(1):1-6. 被引量:8
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