摘要
本文采用Flowmaster软件,针对多用途模块式小型堆(ACP100)的非能动堆芯冷却相关系统,包括非能动堆芯冷却系统(PXS系统)、反应堆冷却剂系统(RCS系统)和自动卸压系统(RDP系统)开展联合仿真分析,建立了系统主要设备(包括堆芯补水箱、蓄压箱、内置换料水箱、RDP系统控制阀、RCS系统主回路、相连管道及其阀门等)的物理模型,分析了非能动堆芯冷却相关系统在小破口(LOCA)事故工况下堆芯安全注入的流量和压力的瞬态变化特性,以验证现有系统的设计满足安全相关的设计要求。
A simulation analysis is carried out in this paper for the passive core cooling related system,including the passive core cooling system(PXS),reactor cooling system(RCS),and automatic depressurization system(RDP)of the small modular reactor by using Flowmaster.System components’physical models are established(including the core makeup tank,accumulation tank,in-containment refueling water storage tank,RDP control valves,RCS loops,connected pipes and relative valves,etc.).Then,the injection flowrate and pressure variation under small break LOCA accident condition is analyzed to verify the present system design can meet the safety related design requirement.
作者
蔡志云
CAI Zhi-yun(Nuclear Power Institute of China,Chengdu,Sichuan Prov.610041,China)
出处
《中国核电》
2020年第1期50-53,共4页
China Nuclear Power
