铅铋冷快堆堆芯轴向一维单通道稳态分析

Axial One-Dimensional Single-Channel Model for Pb-Bi Cooled Fast Reactor Core Steady State Analysis

通过建立简化的堆芯轴向一维单通道稳态模型并编制相应的程序,对铅铋冷却快堆物理热工耦合问题进行研究。该模型主要包含中子扩散﹑燃料元件导热和冷却剂输热三个部分。并详细介绍了各部分的迭代求解流程。依据文献中提供的MYRRHA反应堆参考设计方案进行堆芯参数计算,得到了与文献相一致的结论,验证了程序,为下一步开展铅铋冷却快堆堆芯的瞬态研究奠定了基础。

A simplified axial one-dimensional single-channel steady model is proposed and conrresponding program is given to study the problem of neutronics/thermal-hydraulics in Pb-Bi cooled fast reactor core. The model includes neutron diffusion, fuel element heat conduction and coolant heat transfer. And introduce the solution processes in detail. Based on MYRRHA reactor reference design in references, carry out the calculation and obtain results are consistent with the reference ones. Further transient studies on Pb-Bi cooled fast reactor are carrying on based on this model.