钠沸腾数学模型及其在BE+1上的验证  

Establishment of Sodium Boiling Model and Validation on BE+1 Experiment for Fast Reactors

作　　者：赵树峰[1] 罗锐[1] 王洲[1] 石晓波[1] 杨献勇[1] 

机构地区：[1]清华大学热科学与动力工程教育部重点实验室,北京100084

出　　处：《核动力工程》2007年第5期10-13,35,共5页Nuclear Power Engineering

摘　　要：快堆在发生单个燃料组件瞬间完全堵流事故时,会引起堆芯内的冷却剂沸腾。钠沸腾所形成的压力和物质分布对后期事故的发展有重要影响。为了对事故进行总体性分析,本文选择两流体六方程模型,用子通道的方法进行网格划分,用D.R.Liles等人开发的半隐数值方法进行求解;在法国的BE+1实验中进行了模型验证;根据计算结果,对事故下钠的两相热工水力行为进行了解释。Under total instantaneous blockage of single subassembly accidental condition in the fast reactors, the sodium will be boiling soon, which results in the relocation of material and pressure, and has great effect on the development of the accident. To present an integral analysis for this accident, the mechanism of sodium boiling has to be understood firstly. The two-fluid and six-equation model is adopted, and the sub-channel approach was used to discretize the computational volume, at last the model is solved by the semi-implicit numerical method developed by D. R. Liles et al. After validated on the BE＋1 experiment, the thermal-hydraulic behavior of sodium under TIB accident is interpreted in detail.

关 键 词：快堆 钠沸腾 子通道 

分 类 号：TL433[核科学技术—核技术及应用] TL364