过冷沸腾数值模拟在EAST第一壁中的应用  

Numerical simulation of subcooled flow boiling and application to the EAST plasma facing components

作　　者：康钦兰[1] 宋云涛[1] 黄生洪[2] 王忠伟[1] 戢翔[1] 

机构地区：[1]中国科学院等离子体物理研究所,合肥230031 [2]中国科学技术大学,合肥230026

出　　处：《核聚变与等离子体物理》2011年第4期310-314,共5页Nuclear Fusion and Plasma Physics

基　　金：国家"九五"重大科学工程面上项目(计投资[1998]1303);青年知识创新工程项目(Y05PCQ0121)

摘　　要：介绍了过冷沸腾换热的数值模拟方法以及在EAST第一壁组件冷却系统中的应用。采用双流体模型,系统分析了过冷沸腾壁面换热过程中存在的各种换热模式,给出了Fluent软件封闭关系式中所需的质量、动量以及能量的交换项的形式。采用用户自定义函数(UDF)模拟壁面沸腾气化过程,对提出的模拟方法与已发表的实验数据对比进行了校核,得出合理的结论。最后分析了过冷沸腾两相流在EAST第一壁中的工程应用,模拟了热沉冷却结构的沸腾换热现象。为EAST PFCs的冷却结构优化提供了依据。Numerical simulation approaches to subcooled boiling and their application to EAST plasma facing components （PFC） was described. A two-fluid model implemented with a wall boiling model based on a wall heat flux partition algorithm was used to solve control equations for mass, momentum and energy, which coupled with additional closure relations describing the exchange of two phases at the interface. A user-defined function （UDF） was written to define the source terms of phase exchange and specify the customized parameters of the multiphase And the physical model was verified by experimental data of Lee et al. Also the simulation of the EAST plasma facing components was done with subcooled flow boiling method for EAST PFCs cooling structure optimization.

关 键 词：EAST第一壁 过冷沸腾 双流体模型 UDF 

分 类 号：TL621[核科学技术—核技术及应用]