Method for treating activated carbon by chemical flocculation of radioactive waste liquid from nuclear facilities

A technology of radioactive waste liquid and chemical flocculation, applied in chemical instruments and methods, radioactive pollutants, inorganic chemistry, etc., can solve the problems of high difficulty in removal, large proportion of colloidal/granular corrosion products, etc., and meet the needs of engineering applications , The effect of waste minimization

Inactive Publication Date: 2019-11-19
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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Problems solved by technology

[0003] The radioactive waste liquid of pressurized water reactor nuclear power plant mainly includes several types such as reactor coolant effluent, ground drainage, hand washing waste liquid and chemical waste liquid. There are two types of fission products and colloidal / granular corrosion products. According to the operating experience of in-service power plants, colloidal / granular corrosion products account for a large proportion and are difficult to remove

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  • Method for treating activated carbon by chemical flocculation of radioactive waste liquid from nuclear facilities
  • Method for treating activated carbon by chemical flocculation of radioactive waste liquid from nuclear facilities

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[0021] In order to make the above objectives, features and advantages of the present invention more obvious and understandable, the present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.

[0022] Such as figure 1 As shown, the method for chemical flocculation treatment of activated carbon from radioactive waste liquid of a nuclear facility provided by an embodiment of the present invention includes the following steps:

[0023] 1. Material selection:

[0024] Activated carbon substrates on the market mainly include coal, wood and coconut shell. In order to meet the special requirements of engineering applications on the mechanical strength and chemical stability of activated carbon, the present invention selects high fixed carbon content, thick wood layer, and inorganic salt content. And imported coconut shell with less ash to ensure that the ash content of the finished product is less than 4% and the strength...

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Abstract

The invention provides a method for treating activated carbon by chemical flocculation of radioactive waste liquid from nuclear facilities. The method includes the following steps: a step of activation process, namely a step of activating a coconut shell carbonized material by a converter at 850 DEG C and forming holes by using high temperature steam to prepare a finished product with an iodine adsorption value that characterizes channel characteristics greater than or equal to 1000 mg / g and a methylene blue adsorption value greater than or equal to 150 mg / g; a step of post-treatment, namely astep of backwashing broken activated carbon particles, cleaning the particles with high-purity 30% hydrochloric acid and finally leaching the activated carbon particles with desalinated water with conductivity less than 2 [mu]s / cm to prepare the product with an acid soluble index less than or equal to 0.5%; and a step of drying, namely a step of using a quick drying fluidized bed and infrared heating combined rapid drying process to prepare the finished product with water content less than or equal to 3%. The method provided by the invention can effectively remove corrosion products in radioactive waste liquid from the nuclear facilities, meet the needs of engineering applications, ensure that waste generated by the process can be reasonably minimized and minimize the waste.

Description

Technical field [0001] The invention relates to a method for chemical flocculation treatment of activated carbon by radioactive waste liquid of nuclear facilities. Background technique [0002] According to my country's "Environmental Radiation Protection Regulations for Nuclear Power Plants" (GB 6249-2011), for coastal plant sites, the concentration of other radionuclides except tritium and carbon 14 in the radioactive effluent at the trough discharge outlet should not exceed 1000 Bq / L. For inland plant sites, the concentration of other radionuclides except tritium and carbon 14 in the radioactive effluent at the trough discharge outlet should not exceed 100Bq / L. According to the typical waste liquid source items of nuclear facilities, the overall waste liquid treatment system should be decontaminated Factor needs to reach 10 3 ~10 4 . According to the guidelines for the minimization of radioactive waste in nuclear power plants, it is required that the waste generated in the vari...

Claims

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Application Information

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IPC IPC(8): C01B32/336C01B32/354B01J20/20C02F1/28
CPCB01J20/20C02F1/281C02F2101/006
Inventor 何艳红叶孙龙王鑫叶其祥朱来叶周敦满翁明辉陈斌
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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