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超临界水冷堆燃料性能验证实验回路的冷却剂丧失事故分析 被引量：2

Loss of Coolant Accident Analysis of Supercritical Water-cooled Reactor Fuel Qualification Test Loop
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摘要 超临界水冷堆燃料性能验证实验(SCWR-FQT)将对1个小型燃料组件在超临界水环境下进行堆内性能测试。本工作应用修改过的ATHLET程序对包含该燃料组件的超临界水冷实验回路进行建模,并对其冷却剂管道破口导致的失水事故进行分析计算。计算结果表明,现有安全系统设计基本能保证在这些事故情况下维持燃料棒实验段的有效冷却。结果显示,修改过的ATHLET程序对超临界水冷系统的模拟具有良好的适用性。 The supercritical water-cooled reactor fuel qualification test （SCWR-FQT） intends to test a small scale fuel assembly under supercritical water environment in a research reactor. The modified ATHLET code was applied to model the supercritical water cooled experimental loop containing this fuel assembly and to perform the calculation analysis of the loss of coolant accident induced by the coolant pipe break. The results indicate that the design of existing safety system can practically ensure the effective cooling of the fuel rod experimental section in the accident scenario. The results also show that the modified ATHLET code has good suitability in simulation of supercritical water-cooled system.
作者 周翀 杨燕华 程旭
机构地区 上海交通大学核科学与工程学院
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第9期1554-1559,共6页 Atomic Energy Science and Technology
基金 欧盟第七框架"超临界水冷堆燃料性能验证实验"项目资助(269908)
关键词 超临界水冷堆 ATHLET 失水事故分析 SCWR ATHLET LOCA analysis
分类号 TL332 [核科学技术—核技术及应用]
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共引文献51

同被引文献13

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  • 10S W, Zhou C, Xu Z H, et al. Modification and Application of the ATHLET-SC Code to Trans-critical Simulations[C]//Proceeding of the 5th International Symposium on Supercritical Water-Cooled Reactors, Canada. 2011.

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原子能科学技术
2013年 第9期

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