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Method for reprocessing spent nuclear fuel and method for reprocessing spent nuclear fuel

机译:乏核燃料的后处理方法和乏核燃料的后处理方法

摘要

PROBLEM TO BE SOLVED: To improve the decontamination factor of products and the recovery factor of Pu by fluorinating a spent nuclear fuel with a fluorinating agent and separating and recovering uranium (U), a mixture of U and plutonium (Pu) and nuclear fission products respectively on the basis of the difference in the volatility of them. SOLUTION: Spent nuclear fuel rods are loaded into a fluorinating device 3, a fluorinating agent 1 selecting fluorides that fluorinate only uranium (U) is supplied, and high-purity uranium is obtained by converting U into an uranium hexafluoride (UF6) and volatilizing it. At the time, the amount of the uranium that must be mixed with plutonium (Pu) is preserved in the fluorinating device 3 and the volatilized UF6 is stored in a cylinder after the purification of it. Then, a fluorinating agent 2 to which a reagent that is strong enough to volatilize all the amount of Pu is applied is supplied to a fluorinating device 3, and all the amount of Pu and the rest of U are fluorinated and volatilized. A recovered mixture of U and Pu is converted into an oxide and is recycled as a mixed oxide (MOX) fuel. Ultimately, non-volatile nuclear fission products that is preserved as high-level wastes in the fluorinating device 3 can stably be stored and disposed of by compressing, fabricating and vitrifying them.
机译:解决的问题:通过用氟化剂对乏核燃料进行氟化并分离和回收铀(U),U和p(Pu)的混合物以及核裂变产物,来提高产品的去污因子和Pu的回收率。分别基于它们的波动性差异。解决方案:将用过的核燃料棒装入氟化装置3中,提供选择仅氟化铀(U)的氟化物的氟化剂1,并通过将U转化为六氟化铀(UF6)并挥发而获得高纯度铀。 。此时,必须与p(Pu)混合的铀的量被保存在氟化装置3中,并且挥发后的UF6在纯化后被储存在圆筒中。然后,将施加了足以使全部Pu的量挥发的强度足够大的试剂的氟化剂2供给到氟化装置3,并且将全部Pu和U的其余量氟化并挥发。回收的U和Pu混合物转化为氧化物,并作为混合氧化物(MOX)燃料循环使用。最终,可以通过压缩,制造和玻璃化来稳定地存储和处置作为高放废物保留在氟化装置3中的非易失性核裂变产物。

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