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Fibe blanket concept for transmuting transuranic elements and long lived fission products

机译:Fibe毯概念用于改变超铀元素和长寿命裂变产物

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A Molten salt (Flibe) fusion blanket concept has been developed to solve the disposition problems of the spent nuclear fuel and the transuranic elements. This blanket concept can achieve the top rated solution, the complete elimination of the transuranic elements and the long-lived fission procects. Small driven fusion devices with low neutron wall loading and low neutron fluence can perform this function. A 344-MW fusion power from D-T plasmas for thirty years with an availability factor of 0.75 can dispose of 70,000 tons of the US inventory of spent nuclear fuel generated up to the year 2015. In addition, the utilization of this blanket concept eliminates the need for a geological repository site for these materials, which is a major advantage.
机译:为了解决乏核燃料和超铀元素的处置问题,人们开发了熔盐(Flibe)融合毯概念。这种全面的概念可以实现最高评价的解决方案,彻底消除超铀元素和长寿命的裂变过程。具有低中子壁负载和低中子注量的小型驱动聚变设备可以执行此功能。利用DT等离子体的344兆瓦聚变能,使用系数为0.75的三十年,可以处置美国到2015年为止产生的70,000吨乏核燃料库存。此外,利用这一总体概念消除了需求对于这些材料而言,这是一个巨大的优势。

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