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Apparatus for removing nitrous acid in reprocessing feed solution

A nitrous acid and feed liquid technology, which is applied in nuclear engineering, radioactive purification, steam distillation, etc., can solve the problems of inappropriate large-scale removal of nitrous acid, and achieve the effect of continuous operation processing capacity, high speed and improving processing scale.

Inactive Publication Date: 2015-02-04
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] At present, for the removal equipment of nitrous acid in the Purex process of nuclear fuel reprocessing, air is bubbled into the plutonium feed liquid storage tank after batch seasoning to achieve the effect of removing nitrous acid, which is not suitable for large-scale Scale removal of nitrite

Method used

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  • Apparatus for removing nitrous acid in reprocessing feed solution

Examples

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Effect test

Embodiment 1

[0030] A device for removing nitrous acid in post-treatment feed liquid, such as figure 1 As shown, the equipment includes a removal tower 2 (the effective height is 2350 mm, and the diameter is 273 mm), an air generating device 1 and a feed liquid receiving tank 17, wherein the upper end of the removal tower 2 is provided with a feed liquid inlet 13, and the lower end is provided with an air inlet 3. There is a feed liquid outlet 16 at the bottom, and a packing 6 is arranged inside, and an electric heating plate 7 is installed on the outer wall of the removal tower 2, so that the temperature of the feed liquid in the tower is 30°C; the feed liquid to be treated is transported by the feed liquid The pump 15 enters the feed liquid inlet 13 through the feed liquid input pipe, and is in countercurrent contact with the air entering from the air inlet 3, wherein a check valve is installed on the feed liquid input pipe. The feed liquid receiving tank 17 is connected with the feed li...

Embodiment 2

[0034] The difference from Example 1 is that one or more sieve plates are built in the removal tower 2 to separate the packing, and the middle part of the removal tower 2 is equipped with neutron absorbing materials. 10 B 4 c. The heating device arranged on the outer tower wall of the removal tower 2 is an electric heating belt wound on the tower wall, so that the temperature of the feed liquid in the tower is 50°C. A demister 10 is arranged on the top of the demister 2 , and a cyclone separator 11 is arranged at the rear end of the demister 10 . The volume flow ratio of the air fed from the air inlet to the feed liquid fed from the feed liquid inlet is 200. The air generating device is an air compressor.

[0035] Adopt the equipment described in embodiment 1, carry out the removal of nitrous acid to post-treatment feed liquid, processing capacity is 100L / h, and wherein feed liquid consists of: nitric acid concentration: 2.1mol / L, U (VI) concentration: 2g / h L, Fe(III) conc...

Embodiment 3

[0037] Different from Example 1, one or more sieve trays are built in the removal tower 2 to separate the packing, and the wall of the removal tower 2 is equipped with neutron absorbing materials. 6 LiF. The heating device arranged on the outer tower wall of the removal tower 2 is a heating water jacket wound on the tower wall, so that the temperature of the feed liquid in the tower is 40°C. The volume flow ratio of the air fed from the air inlet to the feed liquid fed from the feed liquid inlet is 350. The air generating device is an air compressor.

[0038] Adopt the equipment described in embodiment 1, carry out the removal of nitrous acid to aftertreatment feed liquid, processing capacity is 100L / h, and wherein feed liquid consists of: nitric acid concentration: 2.4mol / L, U (VI) concentration: 2g / h L, Fe(III) concentration: 10g / L, the content of nitrous acid after removal by removal tower 2 is 0.09mol / L.

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Abstract

The invention, which belongs to the technical field of nuclear fuel reprocessing, discloses an apparatus for removing nitrous acid in reprocessing feed solution in the nuclear fuel reprocessing Purex process. The apparatus comprises a removal tower, an air generator and a feed solution receiving tank, wherein a feed solution inlet is arranged on the top end of the removal tower, an air inlet is arranged on the lower end of the removal tower, a feed solution outlet is arranged on the bottom of the removal tower, and a heater is arranged on the external wall of the removal tower; the feed solution receiving tank is connected with the feed solution outlet of the bottom of the removal tower through a feed solution output pipe; packing is arranged in the removal tower, and feed solution to be treated enters the removal tower via the feed solution inlet of the removal tower to be in countercurrent contact with the air entering the air inlet. The apparatus has the advantages of good nitrous acid removal effect, high speed, continuous operation and high treatment capability.

Description

technical field [0001] The invention belongs to the technical field of post-treatment of nuclear fuel, and in particular relates to equipment for removing nitrous acid in post-treatment feed liquid in the Purex process of post-treatment of nuclear fuel. Background technique [0002] The reprocessing process currently being studied uses reducing agents such as U(IV)-hydrazine, hydroxylamine-hydrazine or N,N-dimethylhydroxylamine-methylhydrazine to reduce and strip Pu(Ⅲ), and the 1BP obtained after the separation of uranium and plutonium The plutonium in the feed solution is trivalent, and Pu(III) needs to be oxidized to Pu(IV) before the plutonium is purified and concentrated by extraction-stripping in the next step. Adding oxidants such as nitrogen oxides will cause a certain amount of nitrous acid in the feed liquid after oxidation, and the existing nitrous acid will affect the subsequent process, such as causing excessive consumption of reducing agents or loss of plutonium...

Claims

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Application Information

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IPC IPC(8): G21F9/06G21F9/08B01D3/38
CPCG21F9/06B01D3/38G21F9/08
Inventor 常尚文兰天刘金平何辉周贤明李高亮唐洪彬郑卫芳孟照凯陈志旭
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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