超临界水冷堆CSR1000大破口失水事故分析  

Large-Break Accident Analysis of Supercritical Water-Cooled Reactor CSR1000 Using APROS Code

作　　者：党高健[1] 黄代顺[1] 鲁剑超[1] 高颖贤[1] 单建强[2] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041 [2]西安交通大学核科学与技术学院,西安710049

出　　处：《核动力工程》2013年第1期78-82,共5页Nuclear Power Engineering

摘　　要：为了验证中国超临界水冷堆CSR1000的安全特性,评估CSR1000安全系统的性能,采用APROS程序进行了该堆型的冷段大破口失水事故分析。冷段大破口情况下,喷放阶段的显著特征是堆芯冷却剂在冷段破口喷放作用下迅速发生反向流动,热段的高温、低密度流体进入堆芯导致堆芯传热恶化,包壳温度迅速上升。自动卸压系统(ADS)阀门的启动可恢复堆芯冷却剂正向流动,有效缓解堆芯过热。高压给水箱(HFT)可提供事故早期的堆芯冷却剂供给,并为低压安注的启动提供足够的响应时间。喷放结束后,堆芯逐渐被低压安注再淹没。冷段大破口的最高包壳温度为920℃,低于安全限值(1260℃)约340℃,出现在喷放阶段。Large-break accident analysis of China Super-critical water-cooled Reactor with the related electirc power of 1000 MW（CSR1000） were carried out using APROS code to clarify its characteristics and to evaluate the capability of its safety system. At the cold-leg large-break, the reverse-flow in the core happens immediately due to the blowdown of coolant at the break. The reverse-flow drives the high temperature and low density fluid into the core, which results in the heat transfer deterioration in the core and the cladding temperature increasing quickly. After the opening of ADS valves, the positive-flow in the core has been covered, and the excessive core heat-up has been mitigated. The high feedwater tank can provide the coolant supply at the early period; therefore, the low pressure injection system gets more time to be actuated. After the blowdown phase, the core has been re-flooded gradually by low pressure safety, injection system. The maximum cladding temperature of large break accident is lower than the critefion（1260℃） by about 340℃, which appears during the blowdown phase.

关 键 词：中国超临界水冷堆(CSR1000) 双流程堆芯 大破口失水事故 APROS 

分 类 号：TL333[核科学技术—核技术及应用]