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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

周翀 杨燕华 程旭

原子能科学技术Issue(9):1554-1559,6.
原子能科学技术Issue(9):1554-1559,6.DOI:10.7538/yzk.2013.47.09.1554

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

Loss of Coolant Accident Analysis of Supercritical Water-cooled Reactor Fuel Qualification Test Loop

周翀 1杨燕华 1程旭1

作者信息

  • 1. 上海交通大学 核科学与工程学院,上海,200240
  • 折叠

摘要

Abstract

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 . T he results also show that the modified ATHLET code has good suitability in simulation of supercritical water-cooled system .

关键词

超临界水冷堆/ATHLET/失水事故分析

Key words

SCWR/ATHLET/LOCA analysis

分类

能源科技

引用本文复制引用

周翀,杨燕华,程旭..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[J].原子能科学技术,2013,(9):1554-1559,6.

基金项目

欧盟第七框架“超临界水冷堆燃料性能验证实验”项目资助 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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