Horizontal dissolving technology and system for preparing uranyl nitrate

A uranyl nitrate and solution technology is applied in the field of dissolving uranium-containing materials, and can solve the problems of clogging of a liquid outlet, incomplete dissolution reaction, accumulation, etc., and achieve the effects of improving stability, uniform concentration of dissolved solution, and complete dissolution reaction.

Pending Publication Date: 2017-04-19
CHINA NUCLEAR POWER ENG CO LTD +1
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  • Abstract
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Problems solved by technology

During the dissolving process, the circulating pump is used to stir the material to dissolve in the preparation of the PWR fuel element, and the stirring shaft is used to dissolve the material in the preparation of the heavy water reactor fuel element. Whether it is stirred by the circulating pump or the stirring paddle to dissolve the material, the dissolution reaction is not complete. The problem that the material accumulates at the bottom of the dissolution device and the insoluble slag blocks the liquid outlet

Method used

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  • Horizontal dissolving technology and system for preparing uranyl nitrate

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Embodiment

[0025] U 3 o 8 The barrel is hoisted to the screw feeder and the docking is completed. First measure a certain amount of deionized water and add it into the dissolving tank, then measure a certain amount of 65% nitric acid and slowly add it into the dissolving tank. After the addition of nitric acid is completed, circulate hot water into the jacket of the dissolution tank, and when the temperature in the dissolution tank reaches 60-65 °C, start the switch of the screw feeder, U 3 o 8 The powder is fed into the dissolving tank at a certain speed through the screw feeder for dissolution, and the feeding is completed in 1 hour. After stirring for 30 minutes, raise the temperature to 75-80°C, and continue stirring for 3-4 hours; during the dissolution process, adjust the flow rate of circulating cooling water or hot water to control the temperature of the dissolution tank within the range of 65°C-90°C. Personnel observe the reaction situation through the sight glass at both en...

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Abstract

The invention relates to a horizontal dissolving technology and system for preparing uranyl nitrate. The technology comprises the following steps: adding deionized water and nitric acid to a dissolving tank in a metering manner, horizontally forward pushing a uranium-containing material through a spiral feeder to continuously add the uranium-containing material to the dissolving tank, carrying out a dissolving reaction on the uranium-containing material in the dissolving tank, filtering the obtained dissolved solution after the uranium-containing material is completely dissolved, and sending the filtered solution to a solution storage tank for later use. The technology has the advantages of complete dissolving reaction, uniform concentration of the dissolved solution, no feeding obstruction phenomenon, design purpose reaching, working task completion, effective improvement of the stability of the dissolving reaction, smoothness in production operation, and improvement of the production efficiency and the economy safety of the process.

Description

technical field [0001] The invention relates to a uranium-containing material dissolving process, in particular to a horizontal dissolving process and system for preparing uranyl nitrate solution in a ceramic uranium dioxide production process. Background technique [0002] The main technological process of my country's nuclear fuel element manufacturing is ceramic uranium dioxide powder preparation, pellet preparation and component manufacturing. For the production process of pressurized water reactor fuel elements, heavy water reactor fuel elements, high temperature reactor fuel elements and power reactor fuel elements, it is inevitable to produce some uranium-containing waste, and the recovery of uranium-containing waste is first calcined into U 3 o 8 , and then dissolved in nitric acid to produce uranyl nitrate solution, and then separated by precipitation, dried and reduced to produce uranium dioxide powder; in addition, in the production process of high temperature re...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C01G43/00
CPCC01G43/00
Inventor 李芳林牛小平郑亚娟张超蒋涛沈巍巍杜乐
Owner CHINA NUCLEAR POWER ENG CO LTD
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