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

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Affiliation of Author(s):材料科学与技术学院

Journal:Yuanzineng Kexue Jishu

Abstract: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, keff 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. © 2018, Editorial Board of Atomic Energy Science and Technology. All right reserved.

Note:v 52,n 10,p1774-1779

ISSN No.:1000-6931

Translation or Not:no

Date of Publication:2018-10-20