摘要
基于计算流体力学(Computational Fluid Dynamics,CFD)通用计算程序Fluent,研究了模块化熔盐冷却球床堆(Pebble Bed Advanced High Temperature Reactor,PB-AHTR)中心热通道稳态热工水力行为。利用已开发的多孔介质流固两相局域非热平衡模型计算了球床堆中的压降、冷却剂的温场分布以及固相球床的温场分布,计算并比较了不同的多孔介质阻力因子(Ergun与KTA)对通道内的冷却剂流动以及温场分布的影响,并对丧失部分冷却剂情况下通道内的冷却剂及燃料温度进行了计算分析。结果表明使用不同的阻力因子对堆芯压降计算结果和流场的分布影响较大;而冷却剂温场及固相球床温场和球心的温度分布在不同的阻力因子下的差别较小,在PB-AHTR的设计参数下堆芯产生的热量能够被有效的输出,设计具有较大的安全裕度。计算结果对于球床堆的优化设计提供了一定的参考价值。
Background： The thermal hydraulics behavior of the Pebble Bed Advanced High Temperature Reactor （PB-AHTR） hot channel was studied. Purpose： We aim to analyze the thermal-hydraulics behavior of the PB-AHTR, such as pressure drop, temperature distribution of coolant and pebble bed as well as thermal removal capacity in the condition of loss of partial coolant. Methods： We used a modified FLUENT code which was coupled with a local non-equilibrium porous media model by introducing a User Defined Scalar （UDS） in the calculation domain of the reactor core and subjoining different resistance terms （Ergnn and KTA） to calculate the temperature of coolant, solid phase of pebble bed and pebble center in the core. Results： Computational results showed that the resistance factor has great influence on pressure drop and velocity distribution, but less impact on the temperature of coolant, solid phase of pebble bed and pebble center. We also confirmed the heat removal capacity of the PB-AHTR in the condition of nominal and loss of partial coolant conditions. Conclusion： The numerical analyses results can provide a useful proposal to optimize the design of PB-AHTR.
出处
《核技术》
CAS
CSCD
北大核心
2014年第7期79-86,共8页
Nuclear Techniques
基金
中国科学院战略性先导科技专项资助项目(No.XDA02010200)资助
