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Evaluation of Non-Oxide Fuel for Fission-Based Nuclear Reactors on Spacecraft

机译：对瓦斯的裂变基核反应堆非氧化物燃料的评价

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This project investigated the use of uranium nitride (UN) and uranium carbide (UC) reactor fuel and compared their performance to uranium oxide (UO2) in a nuclear reactor for space-based applications. As a baseline for analysis, the Prometheus Project reference reactor module was considered: a gas-cooled fast reactor using highly enriched UO2 fuel with 1 MW of thermal power output and a 15-year core life. An estimate of the temperature feedback effect on reactivity was made for each fuel type at the beginning, middle, and end of core life; results for each fuel were compared. This analysis indicates that UN-fueled reactors may exhibit a stabilizing negative reactivity feedback for increasing temperatures and that this benefit persists in the face of fuel composition changes over core life. The benefit of increased uranium loading density was assessed through a quantitative estimate of overall core weight for each fuel. It was found that weight savings on the order of 1000 kg can be realized for a reactor of this size by using either UC or UN rather than UO2.
机译：该项目研究了氮化铀（UN）和碳化铀（UC）反应器燃料的用途，并将其在核反应堆中对氧化铀（UO2）的性能进行比较，用于基于空间的应用。作为分析的基线，考虑了Prometheus项目参考电抗器模块：使用高度富集的UO2燃料，具有1 MW的热力输出和15年核心寿命的气体冷却的快速反应器。在核心寿命的开始，中间和结束时对每个燃料类型进行对反应性的温度反馈效应的估计;比较每个燃料的结果。该分析表明，未燃料的反应器可以表现出稳定的负反应性反馈，用于提高温度，并且这种益处在面对燃料组合物的变化上核心寿命的变化。通过定量估计每种燃料的总芯重的定量估计来评估增加的铀加载密度的益处。发现，通过使用UC或UN而不是UO2，可以为1000 kg的大约1000kg的重量节省来实现这一尺寸的反应器。

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