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

机译：航天器裂变核反应堆非氧化物燃料的评估

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摘要

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）反应堆燃料的使用，并将其性能与核反应堆中用于空间应用的氧化铀（UO2）进行了比较。作为分析的基准，考虑了Prometheus项目参考反应堆模块：使用高浓缩UO2燃料的气冷快堆，其热功率输出为1 MW，堆芯寿命为15年。在堆芯寿命的开始，中期和结束时，对每种燃料类型的温度反馈对反应性的影响进行了估算。比较了每种燃料的结果。该分析表明，以联合国为燃料的反应堆可能会在温度升高时表现出稳定的负反应性反馈，并且面对堆芯寿命内燃料成分的变化，这种益处仍然存在。通过对每种燃料的整体堆芯重量进行定量估计，可以评估铀负载密度增加的好处。已经发现，通过使用UC或UN而不是UO 2，对于这种尺寸的反应堆可以实现约1000kg的重量减轻。

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