Nuclear power station waste liquid treatment device and use method

By combining evaporation, filtration and ion exchange technologies in the waste liquid treatment device of nuclear power plant, corrosion activation products and radionuclides in the waste liquid of nuclear power plant are removed, and the problem of waste liquid treatment is solved, and efficient purification and safe treatment of waste liquid is achieved. Reduced pollution and treatment costs.

CN119296841APending Publication Date: 2025-01-10XIAN THERMAL POWER RES INST CO LTD +1
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Patent Information

Application Number
CN202411410718.8
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2024-10-10
Publication Date
2025-01-10

AI Technical Summary

Technical Problem

The prior art is difficult to effectively treat and purify radioactive waste liquids generated by nuclear power plants, especially to remove corrosion activation products and radionuclides, resulting in radioactive pollution posing a threat to the environment and human health.

Method used

A waste liquid treatment device for nuclear power plant is designed, including an evaporation device, a supernatant treatment unit, a concentrated liquid treatment unit, a mixing bed, a monitoring device and a dehydrator. Through technical means such as evaporation, filtration, ion exchange and dehydration, Cr is efficiently removed. Corrosion activation products such as Mn, Fe, Co, Ag, and cationic nuclides such as Cs+ and Sr2+ to achieve purification of waste liquid.

Benefits of technology

Significantly reduce the radioactivity level of waste liquid, improve purification efficiency, reduce processing difficulty and cost, ensure resource recycling and environmental protection benefits, and reduce the threat of radioactive pollution to the environment and health.

✦ Generated by Eureka AI based on patent content.

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Abstract

The invention discloses a nuclear power station waste liquid treatment device and a use method, and belongs to the technical field of nuclear power station chemical decontamination. According to the device, a supernatant discharge port of an evaporation device is connected with the inlet end of an evaporated liquor collecting box, and the outlet end of the evaporated liquor collecting box is connected with the inlet end of a mixed bed; a concentrated solution outlet of the evaporation device is connected with the inlet end of the mechanical acceleration clarification tank, the outlet end of the mechanical acceleration clarification tank is connected with the inlet end of the multi-medium filter, and the outlet end of the multi-medium filter is connected with the inlet end of the mixed bed; the outlet end of the mixed bed is connected with the inlet end of the monitoring device; the outlet end of the monitoring device is connected with the inlet end of the mechanical acceleration clarification tank; the bottom of the mechanical acceleration clarification tank is connected with the inlet end of the dehydrator, and the outlet end of the dehydrator is connected with the inlet end of the mechanical acceleration clarification tank. According to the invention, corrosion activation products existing in a colloid form can be efficiently removed, and cation nuclides and anion nuclides are removed through the mixed bed, so that the purpose of purifying the nuclear power waste liquid is achieved.
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Citation Information

Patent Citations

  • Evaporation treatment method for radioactive waste liquids of nuclear power plant

    CN103794260A

  • Treatment system for radioactive liquid waste of nuclear power plants and secondary waste thereof

    CN107195352A

  • Treatment device and treatment method for near-zero discharge of decontamination waste liquid containing uranium and detergent

    CN109411106A

  • Method for decontaminating liquid wastes of nuclear power stations

    RU2164045C2

  • Method of and apparatus for the treatment of radioactive waste water from nuclear power plants

    US4440673A