会议专题

An Implementation of the Interfacial Area Transport Equation into the CUPID Code

A component-scale thermal-hydraulics analysis module, CUPID, has been being developed for a transient three-dimensional two-phase flow analysis of nuclear reactor components. This paper summarizes the implementation into the CUPID of turbulence model, non-drag forces, and interfacial area transport and reports some verification and validation results. The lateral behavior of interfacial area concentration is important for the general flow structure in the case of the pipe flow. The turbulence model, the non-drag model, and the interfacial area concentration model are known as the important models related to this lateral interfacial area concentration distribution. Turbulence models are directly related to the lateral direction velocity profiles. The zero equation and k-ε turbulence models based upon the eddy viscosity are adopted for considering the turbulence effect. The wall function is also used for the wall boundary condition of the turbulence model. While the drag force and the virtual mass force are related to the relative movement to the primary flow motion, the non-drag forces are related to the gas movement to the lateral direction of the primary flow motion. The three non-drag forces of lift force, wall lubrication force and turbulence dispersion force are considered in the CUPID code. The interfacial area transportation equation is set up to calculate the interfacial area concentrations distribution. This transport equation is strongly affected by the turbulence model and the non-drag forces. The gas velocity, gas volume fraction, Sauter mean diameter of bubbles, and the interfacial area concentration distributions are the primary parameters to be considered in this paper. The lateral profiles of these four parameters are used to assess that the turbulence model, the non-drag force models, and the interfacial area transport equation are properly implemented and work well.

CUPID code Turbulence Non-drag force Interfacial area concentration Verification andvalidation

I.K. Park H.K. Cho H.Y. Yoon J.J. Jeong D.J. Euh

Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-gu, Daejon, 305-353,Korea

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

571-582

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)