期刊名称：Bulletin of the Institute of Heat Engineering
印刷版ISSN：2083-4187
出版年度：2014
卷号：94
期号：5
页码：16
语种：English
出版社：Warsaw University of Technology
摘要：Abstract The purpose of this report was to present the results of a numerical simulation of thermal hydraulics processes in the liquid metal cooled fast reactor core, combined with the simple neutron population computing for infinite pin cell lattice. Two types of the coolant have been studied: liquid sodium and the liquid lead, with all requirements regarded to safety conditions. Temperature distributions along the cooling channel and distributions in radial direction have been prepared and in the next step the criticality calculations using MCNP Monte Carlo code for MOX fuel have been conducted.
关键词：nuclear engineering; neutronics; thermohydraulics;;lead fast reactor; sodium fast reactor; pin design; MCNP
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