Neutronic analysis of a heat-pipe cooled reactor

Josef Sabol, Jan Frýbort
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Abstract

Heat-pipe cooled reactors belong to the group of nuclear reactors using heat pipes filled with liquid metals (such as sodium or potassium) to cool the core. Due to the passive heat removal system, there is no need to use closed loops with pumps, and the reactor can be operated with reduced operational requirements. Consequently, this system can be used in remote locations without access to an electrical grid, or it can be used for space applications.This paper deals with a neutronic study of the Special Purpose Reactor Design-B concept from the Idaho National Laboratory. Using Monte Carlo code Serpent 2 and ENDF/B VIII.0 library, a fixed-temperature model was created to calculate the safety characteristics of the system. This included reactivity coefficients, power distribution, neutron flux spectrum, and criticality safety. In a simplified depletion calculation, an effect of fuel depletion on safety systems was determined as well as a decay heat.
热管冷却反应堆的中子分析
热管冷却反应堆属于使用充满液态金属(如钠或钾)的热管来冷却堆芯的核反应堆。由于采用了被动散热系统,因此无需使用带泵的闭式循环,反应堆的运行要求也可降低。因此,该系统可用于没有电网的偏远地区,也可用于太空应用。本文论述了对爱达荷国家实验室提出的特殊用途反应堆设计-B 概念的中子研究。利用蒙特卡洛代码 Serpent 2 和 ENDF/B VIII.0 库,创建了一个固定温度模型来计算系统的安全特性。其中包括反应系数、功率分布、中子通量谱和临界安全性。在简化的耗竭计算中,确定了燃料耗竭对安全系统的影响以及衰变热。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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CiteScore
0.40
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