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Method of reprocessing spent nitride nuclear fuel in molten chloride

机译:在熔融氯化物中再加工氮化物核燃料的方法

摘要

A method for retreating spent nitride nuclear fuel in a molten salt, which comprises chlorinating the fuel in a melt of a mixture of alkali metals and / or alkaline earth metal chlorides containing cadmium dichloride. Proposed. Chloridation is carried out in an apparatus for reprocessing spent nitride nuclear fuel using an inert gas atmosphere. The device has a heating zone containing a reactor in which molten chloride and spent nitride nuclear fuel are submerged, and a cold zone located beneath the reactor. In the chlorination process, the zone of the device containing the reactor is heated to a temperature above 700 ° C, the spent nitride nuclear fuel is retained in the melt until it is completely chlorinated, and the cold zone of the device is chlorinated. It is used to crystallize the metal cadmium formed between. The technical result of the present invention is to increase the conversion rate of spent nitride nuclear fuel in molten chloride to 100%, which requires an additional step of repeated filtration and reprocessing of spent nuclear fuel. Reduce or completely eliminate sex. [Selection diagram] Fig. 1
机译:一种在熔融盐中撤回废氮化物核燃料的方法,包括氯化碱金属和/或含有镉二氯化镉的碱土金属氯化物的熔体中的燃料。建议的。在一种用于使用惰性气体气氛进行再处理的氮化物核燃料的装置中进行泛温。该装置具有含有反应器的加热区,其中挤出氯化水和氮化物核燃料被浸没,以及位于反应器下方的冷区。在氯化过程中,将含有反应器的装置的区域加热至高于700℃的温度,将氮化物核燃料保留在熔体中直至其完全氯化,并且将装置的冷区氯化。它用于结晶在之间形成的金属镉。本发明的技术结果是将氯化水中的氮化物核燃料的转化率提高至100%,这需要额外的反复过滤和废旧核燃料再处理步骤。减少或完全消除性行为。 [选择图]图1

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