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Nuclide-containing heavy metal high-concentration acid separation system and separation method

A separation system and separation method technology are applied in the field of radiation wastewater treatment, which can solve the problems of low separation efficiency of acid and salt, inability to separate acid and salt, and high salt permeability, so as to facilitate automatic production, avoid direct contact, The effect of high recovery rate

Inactive Publication Date: 2020-06-05
金达泰克电子系统(北京)有限公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This is a combined treatment method of reverse osmosis and continuous electric desalination. The above-mentioned invention only mentions the process of desalination, and does not mention whether the method can be used to deal with the separation of high-concentration acid and salt
[0007] However, when traditional anion exchange membrane diffusion dialysis is used to separate acid-containing heavy metal salts, the separation efficiency of acid and salt is low, and the penetration rate of salt is relatively high, so acid and salt cannot be separated well.
[0008] In addition, because radioactive waste water has radioactive hazards, especially high-radioactive waste water in nuclear waste water, how to realize automatic loading, unloading and replacement of membrane stacks in the field of radioactive waste water treatment, as well as automatic membrane change without changing Membrane partitions keep operators away from the hazards of radioactive waste water, which is a matter of great concern to researchers;

Method used

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  • Nuclide-containing heavy metal high-concentration acid separation system and separation method
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  • Nuclide-containing heavy metal high-concentration acid separation system and separation method

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Embodiment 1

[0178] Take the automatic loading and unloading membrane stack of the present invention, take the continuous plate diffusion dialysis anion exchange membrane GN-JAM-DD120 (produced by Jinda Tech Electronics System (Beijing) Co., Ltd.), the surface width is 500mm, and the total membrane length is 200m; The partitions are GN-WNC-400×800 from Kindatec, with an effective membrane area of ​​0.266 square meters per sheet, a total of 8 sheets, with an area of ​​2.13m 2 ; The size of the membrane separator is 400mm×800mm, the thickness is 6mm, the thickness of the inner network is 5mm, and the number of membrane separators is 7. The processing flow refers to figure 1 shown. in, figure 1 In , "yin" refers to the anion exchange membrane.

[0179] The water source to be treated is the waste liquid produced by adding acid to dissolve the spent fuel in the reprocessing of spent fuel, in which the original acid is a high-acid and high-level radioactive waste liquid, and its composition is...

Embodiment 2

[0185] The method used in this embodiment is the same as in Example 1, the only difference being that the membrane used is a cation exchange membrane I, specifically the continuous plate diffusion dialysis cation exchange membrane GN-JCM-DD120 of Jinda Tech Electronics Systems (Beijing) Co., Ltd., and the same Therefore, the raw acid and raw water form a cross-flow on both sides of the membrane, and the obtained acid production and residual acid, as well as the recovery rate are shown in Table 2 below:

[0186] Table 2 only treats the result of raw acid with cation exchange membrane I

[0187]

[0188] Note: In Table 2, the "acid generation" and "residual acid" are obtained from the membrane stack formed by the separate cation exchange membrane I and the membrane separator.

Embodiment 3

[0190] The source of raw materials used in this embodiment is the same as in Example 1, and the feed rate is the same. The difference is that the membrane stack composition adopted in this embodiment includes cation exchange membrane I and membrane separators to form the first membrane group and anion exchange membrane and membrane separator. The plates form the second membrane group, wherein the number ratio of the membrane separators in the first membrane group to the membrane separators in the second membrane group is 1:1; then press figure 2 as well as Figure 12 Shown in and out of the water operation, the results are shown in Table 3.

[0191] Table 3 Utilizes separation system of the present invention to separate and process raw acid result

[0192]

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Abstract

The invention provides a nuclide-containing heavy metal high-concentration acid separation system and separation method, wherein a dialysis chamber I (21)and a diffusion chamber I (22)are formed by arranging membrane separation plates (1)and cation exchange membranes I (2)at intervals, wherein a dialysis chamber II (23)and a diffusion chamber II (24)are formed by arranging the membrane partition plates (1)and anion exchange membranes (3)at intervals, and a liquid outlet II' of the diffusion chamber I (22) is connected to a liquid inlet III of the dialysis chamber II (23), so that treatment onraw acid (high-concentration acid of nuclide-containing heavy metals)is realized; according to the separation system and the separation method provided by the invention, acid and the nuclide-containing heavy metals can be efficiently separated, a large amount of raw water (nuclide-containing heavy metal low-acid wastewater)can be utilized to realize pollution control by pollution, and secondary pollution is avoided; moreover, the separation system provided by the invention can realize automatic membrane loading and unloading, so that operators are prevented from being in direct contact with radioactive wastewater, and radioactive hazards are avoided.

Description

technical field [0001] The invention relates to a treatment method and equipment for radioactive waste water, in particular to a high-concentration acid separation system and separation method containing nuclide heavy metals. Background technique [0002] High-concentration acid heavy metal radiation wastewater refers to the acid content of 1 to 7mol / L, the heavy metal content of 0.1 to 100g / L, and the radioactive level higher than 3.7×10 2 Bq / L radioactive waste water from the nuclear industry is a relatively difficult waste water, which has become a technical bottleneck restricting the development of rare earth metallurgy and nuclear industry. [0003] The traditional treatment methods include neutralization, ion exchange, evaporation and other methods. These treatment methods require the addition of a large amount of chemical agents or inorganic adsorbents, ion exchange resins, cleaning and descaling agents, etc. On the one hand, a large amount of acid resources are waste...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C02F1/469G21F9/06C22B3/42C22B60/02
CPCC02F1/4693G21F9/06C22B60/0252C22B3/42Y02P10/20
Inventor 郭春禹马黎
Owner 金达泰克电子系统(北京)有限公司
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