应用GOTHIC程序三维模型模拟综合性能试验热工响应过程  

Application of GOTHIC 3D Model to Simulate Thermal-hydraulic Response of Containment Safety Verification via Integral Test

作　　者：王国栋[1] 杨建锋[1] 韦胜杰[1] 王章立[1] 王喆[1] 张迪[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《原子能科学技术》2017年第11期1960-1967,共8页Atomic Energy Science and Technology

摘　　要：本文选取重大专项综合性能试验开展的主蒸汽管道断裂事故全过程瞬态模拟工况作为基准工况,应用GOTHIC程序进行了详细的三维建模,模拟了试验壳大空间和热阱储热、蒸汽在壳体内壁面冷凝、壳体外壁面水膜蒸发等传热传质过程。通过对比试验数据和程序计算结果,研究试验壳大空间的热工响应特性和程序模型的适用性。研究结果表明:程序模型能很好地分析试验壳温度、压力变化趋势,尤其是在蒸汽大流量喷放后阶段,程序分析结果和试验结果符合很好。另外,喷口的射流类型会显著影响大空间温度分层现象,进而影响蒸汽在试验壳体内壁面的冷凝过程。该研究结果可为后续应用GOTHIC程序分析非能动核电厂安全壳响应的可行性提供参考和借鉴。The purpose of this study is to establish a detailed 3D model of containment safety verification via integral test （CERT） using containment code GOTHIC. A full- process of main steamline break （MSLB） accident case was selected as a benchmark. The 3D model simulates such key heat removal process as energy absorption by gas volume and heat sinks inside vessel, steam condensation on the inside shell surface, heat conduction through the steel shell, and evaporation of water film covered on the outer vessel shell surface. The model prediction results were compared and evaluated based on test data. The results show that the 3D model can predict vessel temperature and pressure response trend well. Model predictions agree well with test results during postblowdown period. It also shows that the break jet types affect temperature stratification phenomenon inside vessel dramatically, which has an effect on steam condensation on vessel inside wall. The analysis is of significance on application of GOTHIC code to containment response simulation in passive nuclear power plant.

关 键 词：非能动安全壳冷却系统 GOTHIC程序 综合性能试验 排热过程 

分 类 号：TL364.4[核科学技术—核技术及应用]