Device for preparing tetravalent uranium through electrolytic method, and spent fuel post-treatment system

A tetravalent uranium and electrolysis technology, applied in the electrolysis process, electrolysis components, reactor fuel elements, etc., can solve the problems of increasing the processing load of the uranium purification process, poor separation effect of uranium and plutonium, and unreasonable flow channel design. Increased yield, improved effectiveness, reduced dead volume effectiveness

Inactive Publication Date: 2021-03-26
CHINA NUCLEAR POWER ENG CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0009] However, at the present stage, the electrolytic equipment used for electrolytic preparation of tetravalent uranium still has at least the following problems: unreasonable flow channel design, easy to form channel flow; cathode and anode leakage; electrolytic heat cannot be discharged in time, resulting in temperature rise and side reactions The reduction rate of hexavalent uranium in the electrolyte is low, and it is difficult to exceed 75%. The concentration of hexavalent uranium in the tetravalent uranium solution after electrolysis is high and the concentration of tetravalent uranium is low, which leads to the separation of uranium and plutonium. Ineffective, increasing processing load on subsequent uranium purification process

Method used

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  • Device for preparing tetravalent uranium through electrolytic method, and spent fuel post-treatment system
  • Device for preparing tetravalent uranium through electrolytic method, and spent fuel post-treatment system
  • Device for preparing tetravalent uranium through electrolytic method, and spent fuel post-treatment system

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Embodiment 1

[0046] like figure 1 As shown, this embodiment discloses a device for preparing tetravalent uranium by electrolysis, including an electrolytic cell, the electrolytic cell includes a cell body 1, a cathode plate 4 and an anode plate 5 are arranged in the cell body 1, and a cell body 1 is also provided with Multiple partitions2. A plurality of separators 2 are arranged in parallel, and are arranged in the tank body 1 in sequence, and the tank body 1 is divided into a plurality of compartments 3. The tank body 1 is built with an electrolyte, and the electrolyte solution is filled in each compartment 3, and each Each compartment 3 is provided with a cathode plate 4 and an anode plate 5 . A plurality of compartments 3 are communicated in sequence, and each compartment 3 communicates with the upper / lower part of its adjacent upstream compartment, and communicates with the lower / upper part of its connected downstream compartment.

[0047] Specifically, the shape and size of the par...

Embodiment 2

[0065] This embodiment discloses a spent fuel reprocessing system, which includes a storage device and the device for preparing tetravalent uranium by electrolysis described in Embodiment 1. Among them, the storage device is used to store the uranium-plutonium feed liquid containing hexavalent uranium. In actual operation, the storage device may refer to the device for storing the feed liquid containing hexavalent uranium in the tetravalent uranium preparation system in the spent fuel reprocessing process. For example, the feed tank; the feed port 7 of the device for preparing tetravalent uranium by electrolysis is connected with the output end of the storage device, so that the feed solution containing hexavalent uranium is passed through as the electrolyte.

[0066] Further, the system of this embodiment also includes a uranium-plutonium separation device:

[0067] The uranium-plutonium separation device is connected to the outlet 8 of the device for preparing tetravalent ur...

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Abstract

The invention discloses a device for preparing tetravalent uranium through an electrolytic method. The device comprises an electrolytic cell, which comprises a cell body, wherein a plurality of partition plates are arranged in the cell body, are sequentially arranged in the cell body and divide the cell body into a plurality of compartments, an electrolytic solution is arranged in each compartment, a cathode plate and an anode plate are arranged in each compartment, the compartments are sequentially communicated, each compartment is communicated with the upper portion / lower portion of the adjacent upstream compartment, and each compartment is communicated with the lower portion / upper portion of the downstream compartment connected with the compartment. The invention further discloses a spent fuel post-treatment system comprising the device for preparing the tetravalent uranium through the electrolytic method. According to the invention, the reduction rate of reducing hexavalent uraniuminto tetravalent uranium can be increased to 85% or above, so that the yield of the tetravalent uranium is increased so as to reduce the dosage of a reducing agent in uranium-plutonium separation andimprove the uranium-plutonium separation effect.

Description

technical field [0001] The invention belongs to the technical field of the nuclear industry, and in particular relates to a device for preparing tetravalent uranium by an electrolytic method and a spent fuel reprocessing system. Background technique [0002] At present, most nuclear fuel reprocessing plants in the world adopt the PUREX process, which is mainly composed of a co-decontamination system, a uranium-plutonium separation system, a plutonium purification system, a uranium purification system and a uranium-plutonium tail end. Among them, the separation of uranium and plutonium is to use a reducing agent to reduce the plutonium in the uranium-containing plutonium organic material liquid from tetravalent to trivalent, and enter the water phase, while the uranium remains in the organic phase in the form of hexavalent, thereby realizing the separation of uranium and plutonium . Ferrous sulfamate is the most common reducing agent in the separation process of uranium and ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C25B1/01C22B60/02G21C19/50
CPCC22B60/0204C22B60/0291C25B1/00G21C19/50Y02E30/30
Inventor 蔡梦琦李思凡刘郢刘继连王冬邢运曈王兴旺
Owner CHINA NUCLEAR POWER ENG CO LTD
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