会议专题

Sensitivity Analysis of CFD Two-Phase Flow in a BWR Fuel Bundle

The goal of this work was to perform an investigation of the sensitivities of the average outlet void fraction and flow pattern prediction in the fuel assembly on important model parameters. The model sensitivities were examined on the following groups of parameters: numerical parameters (e.g. Mesh discretization), operating conditions (input power, outlet pressure, mass flow rate and inlet temperature) and closure models for the interphase momentum (e.g. Drag, virtual mass, lift, turbulent dispersion, wall lubrication). The average outlet void fraction was evaluated by the CFD code for the steady-state and model sensitivities were identified. A significant sensitivity was recognized especially for changes of inlet temperature of coolant and system pressure. Moreover, the turbulent dispersion force and the wall lubrication force had a significant influence on vapor and liquid velocity profiles and also on the distribution of void at the outlet of the fuel assembly.

Two-phase flow Boiling Water Reactor CFD Sensitivity analysis

M. Jaromin T. Kozlowski H. Anglart

Royal Institute of Technology (KTH) in Stockholm AlbaNova University Center, Royal Institute of Technology Department of Physics, Roslagstullsbacken 21 SE 106 91 Stockholm, Sweden

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

2361-2375

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)