CAP1400非能动堆芯冷却整体试验关键现象分析  

Analysis on Key Phenomena of CAP1400 Passive Core Cooling Integral Testing

作　　者：史国宝 徐财红 严锦泉 樊普 朱升 SHI Guobao;XU Caihong;YAN Jinquan;FAN Pu;ZHU Sheng(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China)

机构地区：[1]上海核工程研究设计院有限公司,上海200233

出　　处：《原子能科学技术》2021年第10期1806-1813,共8页Atomic Energy Science and Technology

基　　金：大型先进压水堆核电站重大专项(2010ZX06002-003)。

摘　　要：在CAP1400小破口失水事故中,非能动堆芯冷却系统所有设备均投入,显现复杂且独特的物理现象,为验证设计和程序以及识别重要现象,开展了CAP1400非能动堆芯冷却系统性能试验。整体试验台架主要特征为:1∶3高度比、最大工作压力9.2 MPa、等压模拟。试验结果表明,在小破口失水事故中堆芯不裸露,试验过程中发现了冷管段分层流产生机制、安注箱排空后氮气注射及其影响以及压力容器下降段流体温度不均匀性等关键物理现象。最后利用RELAP5程序对整体试验关键现象进行了分析和验证。During CAP1400 small break loss of coolant accident,all passive core cooling equipments will put into operation,and present complex and unique phenomena,in order to validate the design and the computer code,and to understand the key phenomena,CAP1400 integral passive core cooling test was performed.The main characteristics of integral facility are 1∶3 scaled height,maximum operation pressure of 9.2 MPa,simulation with equal pressure.In the tests,the phenomena of cold leg stratification,accumulator nitrogen injection,and downcomer asymmetric temperature distribution are found,and no core uncover in small break loss of coolant accident is testified.Finally the validation of the modified RELAP5/MOD3 with the test results was provided.

关 键 词：小破口失水事故 验证试验 冷管段分层流 氮气注射 下降段流体温度不均匀性 

分 类 号：TL364.4[核科学技术—核技术及应用]