竖直环管内低压水过冷沸腾数值模拟研究

Numerical Simulation Research of Subcooled Boiling Water in Vertical Concentric Annulus Pipe under Low Pressure

1. Department of engineering physics, Tsinghua University, Beijing, 100084, China;
2. Science and Technology on Reactor System Design Technology Laboratory of. Nuclear Power Institute of China, Chengdu, 610041, China;
3. Institute of Nuclear and New Energy Technology of Tsinghua University, Beijing, 100084, China

摘要: 通过在计算流体力学软件(CFX)中添加用户程序实现对低压环管内水过冷沸腾的数值模拟。针对Lee等的过冷沸腾实验工况,利用Unal气泡脱离直径模型修正后的Tolubinsky关系式作为汽泡脱离直径关系式,采用Anglart关系式作为汽泡平均直径关系式。通过比较非曳力模型中不同升力模型、湍流耗散力模型对径向空泡份额分布的影响,提出模型的使用建议。将计算结果与实验进行比较,验证模型在低压工况范围内的适用性。
- 过冷沸腾 /
- CFD /
- 空泡份额
Abstract: A numerical simulation of subcooled boiling in annulus pipe in low pressure conditions was performed on Computational Fluid Dynamics code CFX with user defined program. LEE’s subcooled boiling experiment results in 2002 and 2008 were used for calculations. Bubble departure diameter was used Tolubimsky modified correlation based on Unal bubble departure diameter model and bubble average diameter correlation was used Anglart correlation. The influences of different lift force models and turbulent dispersion force models in non drag models on the radial void fraction distribution were compared; a model use suggestion was given. Compared the calculation results and experiment, the simulation results indicate that the models are endowed with a preferable applicability in low pressure conditions
- Subcooled boiling /
- CFD /
- Void fraction