大型先进压水堆安全壳内水蒸气迁移的数值模拟研究  

Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs

作　　者：张适[1] 王德忠[1] 马元巍[1] 

机构地区：[1]上海交通大学机械与动力工程学院,上海200240

出　　处：《核动力工程》2013年第2期30-33,共4页Nuclear Power Engineering

基　　金：国家自然科学基金项目(11175118);教育部科技创新工程重大项目培育资金资助项目(708036)

摘　　要：利用计算流体力学(CFD)方法,采用Uchida关联式模拟水蒸气冷凝研究大型先进压水堆一回路管道破口发生后水蒸气在安全壳内的迁移情况,分析不同冷却剂泄漏率下水蒸气的分布情况。结果表明:各冷却剂泄漏率下,水蒸气分布趋势基本一致;安全壳壁面附近水蒸气浓度随时间波动上升,且较高位置的浓度波动较小。The migration of steam in the containment after the break of primary circulation pipelines of large-sized advanced PWR is studied by CFD method with Uchida correlations to simulate steam condensation analyzing the steam distribution of different coolant leakage rates. The result suggests that the distribution trend of steam is basically the same at various coolant leakage rates, and the steam concentration near the containment wall increases fluctuant for which the higher position has the smaller fluctuation.

关 键 词：安全壳 冷却剂泄漏率 监测 水蒸气迁移 数值模拟 

分 类 号：TL364.4[核科学技术—核技术及应用]