摘要
基于COBRA-IV开发出了适用于铅铋合金冷却组件和堆芯的子通道热工水力分析程序SUBAS,并利用其对铅铋合金冷却组件进行了详细的子通道分析,主要分析了不同燃料棒数目对组件内的温度场和速度场的影响;对湍流交混模型、横流压降系数、换热系数模型等做了相关的参数敏感性分析。研究结果表明:燃料棒数目的增加会导致组件内外质量、动量和能量的交换更加困难,各类通道的温度都有所升高;定位格架不仅增加了组件压降,而且降低了相邻通道之间的横向流动;湍流交混模型对组件的温度场和速度场影响较大,需要重点研究。
Based on the COBRA-IV code, a new Lead- Bismuth alloy cooled fast reactor sub-channel thermal-hydraulic analysis code, SUBAS, is developed. The impacts of different numbers of fuel pins on the temperature and velocity distri- butions are analyzed. The parameter sensitivity analyses of turbulent mixing models, cross-flow resistance coefficient, heat transfer coefficient models and the gap heat transfer coefficient are carried out. The results show that more numbers of fuel pins would embarrass the mass, momentum and energy exchanges in the assembly. Different turbulent mixing models have more impacts on the temperature and velocity distributions, therefore further and deep studies are needed.
出处
《电网与清洁能源》
北大核心
2016年第6期131-135,142,共6页
Power System and Clean Energy
关键词
铅铋合金冷却快堆
子通道分析
热工水力分析
lead-bismuth alloy cooled fast reactor
sub-channel analyses
thermal-hydraulic analysis
