Radioactive waste liquid treating method, radioactive waste liquid treating device and facility

A technology of radioactive waste liquid and treatment device, which is applied in the fields of radioactive waste liquid treatment, radioactive waste liquid treatment device and equipment, can solve the problems of high disposal cost, large amount of radioactive solid waste, shortened cycle of ion exchange resin, etc.

Active Publication Date: 2017-05-17
CHINA GENERAL NUCLEAR POWER OPERATION +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Taking Daya Bay as an example, the TEU desalination bed configuration is two mixed beds in series, with fewer stages, lack of pretreatment function, and no selective desalination function, low comprehensive treatment efficiency, and long purification time
When the TEU evaporator is not available, the waste liquid that needs to be evaporated can only be temporarily stored in the liquid storage tank. Although it is purified through a temporary desalination bed, the temporary desalination bed has a small capacity and long-term operation is likely to cause radioactive doses. Rapid rise, waste liquid treatment is more difficult, need to set up more storage tanks to store radioactive waste liquid
In addition, since the radioactive waste liquid of nuclear power plants

Method used

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  • Radioactive waste liquid treating method, radioactive waste liquid treating device and facility
  • Radioactive waste liquid treating method, radioactive waste liquid treating device and facility
  • Radioactive waste liquid treating method, radioactive waste liquid treating device and facility

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0095] The adsorbent used in this example is a self-developed micron-sized magnetic core-coated ferrocyanide cesium-removing adsorbent (Chinese invention patent ZL201210347269.8). The experimental adsorbent to the target nuclide Cs + removal performance. The adsorbents of 20g / L, 40g / L and 60g / L were flowed into the reactor for batch experiments to study the effect of adsorbents on the Cs in the solution. + the adsorption situation. Radioactive waste liquid using CsNO 3 Prepared by dissolving in tap water (conductivity about 980μs / cm, corresponding to salt concentration 550-750mg / L), Cs + The concentration is 1.5mg / L. Within 13min of stirring the reaction under the condition of 300rpm, select a specific time point to sample (the ratio of the sampling volume to the total volume of the solution is small to negligible), and analyze the Cs + Concentration, calculate the removal rate of Cs (I) by above formula (1). The removal rate under different adsorbent dosage conditions i...

Embodiment 2

[0101] The adsorbent used in this example is a self-developed micron-sized magnetic core-coated ferrocyanide cesium-removing adsorbent (Chinese invention patent ZL201210347269.8). Experimentally determine and verify the gravitational settling time of the adsorbent.

[0102] For the magnetic cesium-removing adsorbent selected in this embodiment, we also tested the experiment of magnetic separation and sedimentation by using an external magnetic field. In the test, an electric coil is wound on the outer wall of the reactor, and an external magnetic field can be generated after electrification, and the adsorbent can be completely absorbed on the inner wall of the reactor within a few seconds, and the rapid separation of solid and liquid phases is completed. Considering that the structural design and operation of the reactor should be simplified as much as possible in the actual operation of nuclear power plants, the magnetic adsorbent was taken as an example to focus on the gravi...

Embodiment 3

[0110] The first adsorbent used in this example and the second adsorbent are self-developed micron-sized magnetic core-coated ferrocyanide cesium-removing adsorbents (Chinese invention patent ZL201210347269.8). A two-stage sequencing batch reactor was used to test its effect on Cs + removal performance. Under laboratory conditions, using the figure 1 The shown radioactive waste liquid treatment device (two-stage sequencing batch reactor) is used for batch experiments. Among them, the radioactive waste liquid uses CsNO 3 Prepared by dissolving in tap water (conductivity about 980μs / cm, corresponding to salt concentration 550-750mg / L), Cs + The concentration was 1.5 mg / L, and the effective volumes of the first reactor and the second reactor were both 1 L. The feeding mass of the first adsorbent and the second adsorbent flowing into the first reactor and the second reactor is both 40 g, and the amount of each batch of treated water is 1 L. In the experiment, the radioactive ...

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Abstract

The invention discloses a radioactive waste liquid treating method, a radioactive waste liquid treating device and a facility. Radioactive waste liquid is treated by the two-stage cascade radioactive waste liquid treating device including a first reactor and a second reactor, the obtained radionuclide content in second radionuclide is small and meets the discharge standard. The energy consumption is low, the handling capacity is large, and the amount of produced radioactive solid waste is small.

Description

technical field [0001] The invention relates to the technical field of waste liquid treatment, in particular to a radioactive waste liquid treatment method, radioactive waste liquid treatment device and equipment. Background technique [0002] During the operation of nuclear power plants, a large amount of medium and low radioactive waste liquid will be produced. If the waste liquid containing radionuclides is discharged directly, it will cause serious harm to human health and the natural environment. Therefore, it must be treated to meet the emission standards before it can be discharged. Traditional methods for concentrating or separating radionuclides in radioactive waste liquid mainly include evaporation, filtration, ion exchange, or a combination of these technologies. Taking the Daya Bay Nuclear Power Plant as an example, the process waste liquid is treated by the "filtration + ion exchange + evaporation" process, the chemical waste liquid is treated by the "filtratio...

Claims

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Application Information

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IPC IPC(8): G21F9/12
CPCG21F9/12
Inventor 戴忠华黄卫刚赵滢方军赵璇李福志尉继英张猛洪振旻王勤湖于兴毫司鹏昆林尧炳陈跃夏子世
Owner CHINA GENERAL NUCLEAR POWER OPERATION
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