CAJ | 학술논문

本文基于三维CFD安全壳程序 GASFLOW开发了热构件壁面上的液膜覆盖与蒸发模型。通过选定 AP1000大破口事故序列，采用耦合了液膜模型的 GASFLOW程序分析了 AP1000核电厂安全壳内温度压力响应及其非能动安全壳冷却系统(PCS)的性能，并与相同事故序列下 WGOTHIC、MEL-COR、CONTAIN等程序的计算结果进行比较。结果表明，耦合了液膜模型的 GASFLOW程序可用于分析PCS的热工水力行为，其基本功能满足计算需要。
본문기우삼유CFD안전각정서 GASFLOW개발료열구건벽면상적액막복개여증발모형。통과선정 AP1000대파구사고서렬，채용우합료액막모형적 GASFLOW정서분석료 AP1000핵전엄안전각내온도압력향응급기비능동안전각냉각계통(PCS)적성능，병여상동사고서렬하 WGOTHIC、MEL-COR、CONTAIN등정서적계산결과진행비교。결과표명，우합료액막모형적 GASFLOW정서가용우분석PCS적열공수역행위，기기본공능만족계산수요。
A model of heat structure wall surface film coverage and evaporation was developed based on 3 dimensional CFD containment code GASFLOW.The containment temperature and pressure response and the passive containment cooling system (PCS) performance of AP1000 during large break LOCA were analyzed by GASFLOW code coupled with film model.The calculation results were compared with the calculated results of other containment codes WGOTHIC,MELCOR,CONTAIN under the same accident scenario.The results show that the modified GASFLOW code coupled with film model is feasible to analyze the thermal-hydraulic behavior in PCS of PWR and the basic functions can meet the requirements for the calculation.