Abstract Selection of a perfect nuclear reactor fuel demands the neutronic analysis of the available fuel materials in particular reactor environment. This paper summarizes the pin-cell analysis of eight ( 08 ) models considering five ( 05 ) different chemical compositions of nuclear fuel, three (03) different neutron moderator and two (02) types of cladding materials using the open-source Monte-Carlo code OpenMC. The fuel element includes UO2, UN, UC2, MOX, and Thorium fuel, whereas light water, heavy water, and graphite were considered as moderator. The effective multiplication factor ( k eff ) was calculated for all the models and validated by the deterministic code Dragon. It was found that, while keeping the dimensions fixed, the graphite and heavy water moderated fuel pin-cells did not reach criticality. So, an appropriate pitch was found where these two cells reached criticality. Depletion and production of different fissionable materials, as well as neutron poison, were studied. Effect of enrichment, moderator to fuel ratio, and boron concentration on the k eff in a typical water-moderated UO2 with zircalloy-4 clad pin-cell were also presented.

中文翻译：

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使用蒙特卡罗代码 OpenMC 对包含不同化学成分的核燃料和中子减速剂的针电池进行建模和中子分析

摘要 选择完美的核反应堆燃料需要对特定反应堆环境中的可用燃料材料进行中子分析。本文总结了八 ( 08 ) 个模型的 pin-cell 分析，考虑了五 ( 05 ) 种不同的核燃料化学成分、三 ( 0 3 ) 种不同的中子慢化剂和两种 ( 0 2 ) 类型的包壳材料，使用开源蒙特卡罗代码 OpenMC。燃料元素包括 UO2、UN、UC2、MOX 和钍燃料，而轻水、重水和石墨被认为是慢化剂。计算所有模型的有效倍增因子 (k eff ) 并通过确定性代码 Dragon 进行验证。结果发现，在保持尺寸不变的情况下，石墨和重水缓和燃料针状电池并未达到临界状态。所以，在这两个单元达到临界值的地方找到了合适的间距。研究了不同裂变材料以及中子毒物的消耗和产生。还介绍了富集、慢化剂燃料比和硼浓度对典型的水慢化 UO2 与锆合金 4 包覆针电池的 k eff 的影响。