用MCNP软件评价熔盐堆中各种候选盐的性能

T. Petrosyan, E. Melyan, K. Katovský
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引用次数: 0

摘要

本研究建立了熔盐堆模型,用于蒙特卡罗n粒子输运[1]计算代码分析。在工作过程中,完成了两项主要任务,即模拟靶材料在800 MeV能量质子束下作为中子变换器(产生器)的行为和计算所设计反应堆的临界性。通过MCNP软件的分析,得到了中子通量和能量分布,以及对不同熔盐组成的熔盐堆的乘数$k_{eff}$。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software
In the study, the model of Molten Salt Reactor was developed for Monte Carlo N-Particle Transport [1] computational code analysis. In the course of work, two main tasks were fulfilled, which are simulation of target material behavior as a neutron convertor (producer) under 800 MeV energy proton beam and criticality calculation of the designed reactor. As a result of analysis through the MCNP software, neutron flux and energy distributions obtained, as well as the value of $k_{eff}$ multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed.
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