As an alternative to traditional uranium dioxide (UO₂) fuels, mixed oxide (MOX) fuels were developed to dispose of industrial and military stores of plutonium (Pu) through the incorporation of plutonium dioxide (PuO₂) powder into a UO₂ base fuel. The high temperature and chemical stability characteristic of oxide fuels would be maintained, while the added Pu would ultimately be eliminated from long term storage. Plutonium could be extracted from spent light water reactor (LWR) fuels, acting as an additional step to close the fuel cycle and mitigate potential environmental or proliferation concerns. This review summarizes the primary features associated with fast reactor MOX fuels, including fuel restructuring, actinide redistribution, solid fission products, plutonium agglomerates, joint oxide gain, and fuel-cladding chemical interaction. A summary of research efforts within the last 10 years and directions for future research are discussed.

作为传统二氧化铀（UO ₂）燃料的替代品，混合氧化物（MOX）燃料通过将二氧化lu（PuO ₂）粉末掺入UO ₂来处理industrial（Pu）的工业和军事储存。基础燃料。氧化物燃料的高温和化学稳定性能得到保持，而添加的Pu最终可以从长期储存中消除。可以从乏水反应堆（LWR）燃料中提取extracted，作为关闭燃料循环并减轻潜在的环境或扩散问题的附加步骤。这篇综述总结了与快堆MOX燃料相关的主要特征，包括燃料结构调整，act系元素的重新分布，固体裂变产物，p附聚物，联合氧化物的获得以及燃料包壳的化学相互作用。讨论了过去10年中的研究工作摘要以及未来的研究方向。