非能动安全壳冷却系统模拟分析程序PCCSAP-3D及其验证

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Demonstration of Simulation Analysis Program PCCSAP-3D for Passive Containment Cooling System（PCCS）

1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China;
2. State Nuclear Power Technology R&D Center, Beijing, 100190, China

摘要: PCCSAP-3D是我国自主开发用于分析评价非能动安全壳冷却系统(PCCS)的专用程序。通过对AP1000反应堆系统进行建模,使用PCCSAP-3D模拟分析AP1000在假想的冷却剂丧失(LOCA)以及主蒸汽管道破裂事故(MSLB)等设计基准事故下非能动安全系统的运行瞬态,并与西屋公司开发的非能动冷却系统分析程序WGOTHIC的计算结果进行对比。分析结果显示,两者吻合良好,PCCS能够有效地将假想事故下安全壳内的压力控制在设计安全限值以下。初步验证PCCSAP-3D程序对于AP1000反应堆PCCS冷却性能评价的可用性。
- 非能动安全壳冷却系统(PCCS) /
- 分析程序 /
- 先进压水堆
Abstract: PCCSAP-3D is a dedicated analysis code developed for the Westinghouse AP1000 PCCS. In this paper, the models on the AP1000 reactor system are described. The PCCS performances during the postulated design basis accidents（LOCA and MSLB） simulated and analyzed from PCCSAP-3D are compared with that from the WGOTHIC developed by Westinghouse. The results show good agreements, which indicate that the contain-ment pressure during the postulated design basis accident can be limited effectively under the design value by the PCCS performance and also the capacity of the PCCSAP-3D for the analysis and the evaluation on the PCCS performance is validated preliminarily.
- PCCS /
- Analysis code /
- Advanced pressurized water reactor