%0 Journal Article
%T 基于MELCOR程序的AP1000核电厂安全壳瞬态事故分析<br>AP1000 containment accident transient analysis using MELCOR
%A 肖红
%A 曹志伟
%A 冯英杰
%A 杨志义
%A 朱建敏
%J 清华大学学报（自然科学版）
%D 2018
%R 10.16511/j.cnki.qhdxxb.2018.26.041
%X 以AP1000安全壳及其非能动安全壳冷却系统为研究对象，采用MELCOR 2.1程序和辅助建模程序SNAP进行了详细的三维建模，模拟了安全壳冷却过程中对流传热、蒸汽冷凝及液膜蒸发等传热传质过程，使用液膜跟踪模型模拟非动能安全系统（passive containment cooling system，PCS）的特性，分析了冷段双端剪切断裂事故下的安全壳热工水力瞬态过程，给出了事故后各阶段主要参数的计算结果。此外，还对液膜覆盖率和液膜覆盖时间的影响进行了研究。结果表明：MELCOR程序能很好地模拟非能动安全壳冷却系统的热工水力现象，本研究使用了与设计单位完全不同的软件体系，独立地验证了该堆型在大破口事故下的安全性，可为后续应用程序分析核电厂安全壳系统响应特性提供参考和借鉴。<br>Abstract：The AP1000 containment and passive containment cooling system (PCS) were modeled using MELCOR 2.1 and SNAP with detailed 3D modeling to analyze the convective heat transfer, condensation and film evaporation for containment cooling. The film tracking model was used to simulate the PCS characteristics. The containment thermal hydraulic transients during a LOCA were analyzed to predict the main parameters at each stage after the accident. The effects of the film coverage fraction and the film coverage time were also studied. The results show that the MELCOR program can accurately simulate the thermal hydraulics of the AP1000 passive containment cooling system. The results provide a reference for analyzing the characteristics of the nuclear power plant containment system. This study also independently verifies the safety of this reactor design by using an analysis code that is totally different from the design codes.
%K 瞬态
%K 冷凝传热
%K 非能动安全壳冷却
%K 液膜跟踪
%K &lt
%K br&gt
%K transient
%K condensation heat transfer
%K passive containment cooling
%K film tracking
%U http://jst.tsinghuajournals.com/CN/Y2018/V58/I11/1029