Apparatus and method for directly preparing UO2 by molten salt electrolysis of U3O8

Abstract

The invention provides an apparatus and a method for preparing UO2 through molten salt electrolysis of U3O8. The apparatus comprises an electrolytic tank crucible, chloride molten salt, an inert cathode and an anode device, the inert cathode and the anode device are inserted into the chloride molten salt, and the inert cathode comprises a molybdenum sheet or a tungsten sheet and a corundum sleevewrapping the molybdenum sheet or the tungsten sheet; and the anode device is formed by putting a graphite rod in a quartz glass tube with a closed bottom and with holes formed in the two sides, immersing the small holes in the two sides of the quartz glass tube in the chloride molten salt and sealing the top end of the quartz glass tube. Cl2 generated by electrolysis is applied to dissolution of U3O8 in a chloride molten salt system, so emission of Cl2 can be reduced, and repeated utilization of resources is achieved; and the problem of dissolution of U3O8 in the chloride molten salt can be solved. The process is carried out in an atmospheric environment, other auxiliary dissolving reagents are not introduced, other precipitates are not formed, and the whole process is simple to operate and low in cost.

Description

technical field [0001] The invention relates to a device and method for preparing UO2, in particular to a device and method for directly preparing UO2 by electrolyzing U3O8 with molten salt, belonging to the field of nuclear energy, and in particular to a method for dry reprocessing of spent fuel. Background technique [0002] Nuclear energy is an economical, safe, reliable and clean energy, which has attracted more and more attention from the society, and the nuclear fuel cycle is the core issue restricting the development of nuclear energy, especially the current fast breeder reactor (referred to as fast reactor) has been established It is one of the preferred reactor types for the fourth-generation advanced nuclear energy system in the world, and the fast reactor spent fuel has the characteristics of high burnup, high irradiation, and high plutonium content, and the traditional wet reprocessing technology is difficult to meet the needs of the fast reactor nuclear fuel cycl...

AI Technical Summary

Problems solved by technology

[0002] Nuclear energy is an economical, safe, reliable and clean energy, which has attracted more and more attention from the society, and the nuclear fuel cycle is the core issue restricting the development of nuclear energy, especially the current fast breeder reactor (referred to as fast reactor) has been established It is one of the preferred reactor types for the fourth-generation advanced nuclear energy system in the world, and the fast reactor spent fuel has the characteristics of high burnup, high irradiation, and high plutonium content, and the traditional wet reprocessing technology is difficult to meet the needs of the fast reactor nuclear fuel cycle , and dry reprocessing technology has the advantages of high temperature resistance, good radiation stability and less radioactive waste, so for spent fuel reprocessing, dry reprocessing technology is a key technology for the future fast reactor nuclear fuel cycle with its unique advantages choose

Images