Modeling and criticality calculation of the Molten Salt Fast Reactor using Serpent code
Modeling and criticality calculation of the Molten Salt Fast Reactor using Serpent code
复制标题
使用 Serpent 代码对熔盐快堆进行建模和临界度计算
DOI：
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发表时间：
2019
期刊：
影响因子：
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通讯作者：
G. Tikhomirov
中科院分区：
文献类型：
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作者：
O. Ashraf;A. Smirnov;G. Tikhomirov
在熔盐快堆（MSFR）中，液体燃料通过筒芯循环并将裂变热量传输到中间外部热交换器（IHX），因此液体盐可以携带燃料并传递热量。MSFR应该在一个封闭的钍基燃料循环中工作，对裂变产物和堆芯中的所有锕系元素进行全面的后处理。本文的目的是；对MSFR的一次回路进行建模（基于欧洲模型），以确定达到临界所需的启动燃料的成分。综上所述，对三种不同类型的裂变材料（233UF4， PuF3和TRUF3）精确确定了临界和长生命周期所需的启动液体燃料的组成。
In Molten Salt Fast Reactors (MSFR), a liquid-fuel circulates through the cylinder core and transport the fission heat to the Intermediate external Heat Exchangers (IHX), therefore liquid salt allows carrying the fuel and transfer heat. The MSFR supposed to work in a closed Th-based fuel cycle with a full reprocessing of fission products and all actinides in the core. The aim of this paper is; modeling the primary circuit of the MSFR (based on the European model) in order to identify the composition of the start-up fuel required to the criticality. In conclusion, the compositions of the start-up liquid fuel required for criticality and long life cycle were determined precisely for three different types of fissile materials (233UF4, PuF3 and TRUF3).