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INTERIM STORAGE AND LONG-TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL IN THE UNITED STATES

机译:美国研究反应堆燃料的临时存储和长期处置

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Aluminum clad research reactor spent nuclear fuel (RR SNF) is currently being consolidated in wet storage basins (pools). Approximately 20 metric tons (heavy metal) of aluminum-based spent nuclear fuel (Al-SNF) is being consolidated for treatment, packaging, interim storage, and preparation for ultimate disposal in a geologic repository. The storage and disposal of Al-SNF are subject to requirements that provide for safety and acceptable radio-nuclide release. The options studied for interim storage of SNF include wet storage and dry storage. Two options have also been studied to develop the technical basis for the qualification and repository disposal of aluminum spent fuel. The two options studied include direct disposal and melt-dilute treatment. The implementation of these options present relative benefits and challenges. Both the direct disposal and the melt-dilute treatment options have been developed and their technical viability assessed. Adaptation of the melt-dilute technology for the treatment of spent fuel offers the benefits of converting the spent fuel into a proliferation resistant form and/or significantly reducing the volume of the spent fuel. A mobile melt-dilute system concept has emerged to realize these benefits and a prototype system developed. The application of the melt-dilute technology for the treatment of legacy nuclear materials has been evaluated and also offers the promise for the safe disposal of these materials.
机译:铝复合研究堆乏核燃料(RR SNF)目前正在湿储水池(池)中进行整合。目前正在整合约20公吨(重金属)铝基乏核燃料(Al-SNF),以进行处理,包装,临时存储以及为最终处置准备在地质处置库中。 Al-SNF的存储和处置要符合安全性和可接受的放射性核素释放规定。 SNF的临时存储研究的选项包括湿存储和干存储。还研究了两种选择,以开发铝废燃料鉴定和储存处置的技术基础。研究的两个选项包括直接处置和熔体稀释处理。这些选择的实施带来了相对的好处和挑战。已经开发了直接处置和熔体稀释处理方案,并评估了它们的技术可行性。熔体稀释技术用于乏燃料的处理具有将乏燃料转变成抗扩散形式和/或显着减少乏燃料体积的好处。移动熔体稀释系统的概念已经出现,以实现这些好处,并开发了原型系统。评估了熔融稀释技术在处理遗留核材料中的应用,也为安全处置这些材料提供了希望。

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