基于MOREL2.0对石墨慢化熔盐堆的稳态分析

熔盐堆采用熔融的氟化盐混合物作为燃料和堆芯的冷却剂，由于燃料的流动，熔盐堆在中子学和热工水力学方面与传统固体燃料反应堆有着较大区别。本文基于熔盐堆分析程序MOREL2.0对钍基熔盐堆（TMSR）初步堆芯设计方案进行了稳态计算分析，结果表明：燃料流动对缓发中子先驱核的分布影响较大，并导致169 pcm反应性损失；随燃料在外部回路中滞留时间的增加，k_eff降低，80 s后趋于平稳；TMSR具有负的入口燃料温度系数，具有固有安全性。

Steady Analysis of Graphite-moderator Molten Salt Reactor Based on MOREL2.0

Molten salt reactor (MSR) adopts molten fluoride salt mixture as fuel and coolant, and the features of neutronics and thermal-hydraulics of MSR are different from those of traditional solid-fuel reactors due to flowing fuel. Steady state analysis of a preliminary design of thorium molten salt reactor (TMSR) was performed based on MSR analysis code MOREL2.0. The results show that fuel flow brings a significant influence on the distribution of delayed neutron precursors and leads to 169 pcm of reactivity loss, k_eff decreases as the increase of time spent through external loop and tends to be stable after 80 s, and TMSR has a negative inlet fuel temperature coefficient and inherent safety characteristic.