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A pyrolysis treatment device and method for radioactive waste resin

A technology of radioactive waste resin and treatment method, which is applied in the fields of radioactive purification, nuclear engineering, products, etc., can solve the problems of high energy consumption of incineration method, increased volume of waste resin, and easy cracking of solidified body.

Active Publication Date: 2021-09-10
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, after direct cement curing of untreated radioactive waste resin, its radiation resistance is poor and its long-term stability is poor, and due to the strong swelling property of the resin, the obtained cured body has obvious compatibilization phenomenon, which makes the cured body easy to crack
The high-integrity container method is a method of sealing waste radioactive resin in concrete, polyethylene or high-density composite materials. It is simple to operate, but the volume of waste resin after sealing will greatly increase, thereby increasing transportation and storage costs.
The incineration method can minimize the mass and volume of radioactive waste resin, but the incineration method consumes a lot of energy and produces SO 2 and other harmful gases, and the residue after incineration will still cause harm to the environment

Method used

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  • A pyrolysis treatment device and method for radioactive waste resin
  • A pyrolysis treatment device and method for radioactive waste resin
  • A pyrolysis treatment device and method for radioactive waste resin

Examples

Experimental program
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Effect test

Embodiment 1

[0068] (1) Under a nitrogen atmosphere, use a thermogravimetric analyzer TG to carry out thermogravimetric analysis of the radioactive waste 717 type anion exchange resin, and its thermogravimetric temperature is T 1 =78.9°C, T 2 =299.6°C, T 3 =403.8°C.

[0069] (2) The radioactive waste 717 type anion exchange resin of 0.5kg is placed in the waste resin container 1-2 of the pyrolysis treatment device of radioactive waste resin, open nitrogen input system 4 and microwave generation and control system 2, when nitrogen flow rate is In a nitrogen atmosphere of 30mL / min, the temperature is raised to 78.9°C at a rate of 10°C / min, the microwave power is 5kW, the frequency is 2.45GHZ, and the temperature is maintained for 0.5h. The pyrolysis gas enters the pyrolysis gas treatment system 3 and passes through the filter 3-1( Nuclear-grade high-efficiency filter, filter material is inorganic glass fiber), gas scrubber 3-2 (gas scrubbing liquid is 0.1mol / L sodium hydroxide solution), c...

Embodiment 2

[0074] (1) Under a nitrogen atmosphere, use a thermogravimetric analyzer TG to carry out a thermogravimetric analysis of the radioactive waste 201×7 type strongly basic anion exchange resin, and its thermogravimetric temperature is T 1 =107.8°C, T 2 =203.6°C, T 3 =411.2°C.

[0075] (2) The radioactive waste 717 type anion exchange resin of 0.5kg is placed in the waste resin container 1-2 of the pyrolysis treatment device of radioactive waste resin, open nitrogen input system 4 and microwave generation and control system 2, when nitrogen flow rate is In a nitrogen atmosphere of 20mL / min, the temperature is raised to 107.8°C at a rate of 10°C / min, the microwave power is 5kW, the frequency is 2.45GHZ, the temperature is maintained for 0.5h, the resin quality is reduced to 55%, and the pyrolysis gas enters the pyrolysis gas treatment system 3, Condensed to After room temperature and desiccator 3-4, enter the gas collection tank 3-5 for storage, and use the gas analyzer 3-6 to a...

Embodiment 3

[0081] (1) Under a nitrogen atmosphere, use a thermogravimetric analyzer TG to carry out thermogravimetric analysis of the radioactive waste 732 type cation exchange resin, and its thermogravimetric temperature is T 1 =110.4°C, T 2 =426.2°C.

[0082] (2) Place 1 kg of radioactive waste 732 type cation exchange resin in the waste resin container 1-2 of the pyrolysis treatment device for radioactive waste resin, open the nitrogen input system 4 and the microwave generation and control system 2, and set the nitrogen flow rate at 30mL / min in a nitrogen atmosphere, the temperature is raised to 110.4°C at a rate of 15°C / min, the microwave power is 10kW, the frequency is 2.45GHZ, and the temperature is maintained for 0.5h. The pyrolysis gas enters the pyrolysis gas treatment system 3 and passes through the filter 3-1 (nuclear high-efficiency filter, the filter material is inorganic glass fiber), gas scrubber 3-2 (gas scrubbing liquid is 0.1mol / L sodium hydroxide solution), condense...

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Abstract

The invention provides a thermal cracking treatment device and method for radioactive waste resin, belonging to the technical field of nuclear industry. The device provided by the present invention includes a microwave resonance and heating system 1 , a microwave generation and control system 2 , a pyrolysis gas treatment system 3 , a nitrogen gas input system 4 and a carbon residue collection chamber 5 . The present invention uses microwaves to heat radioactive waste resin, which has the characteristics of safety, cleanliness and high efficiency, and can realize dehydration and pyrolysis of radioactive waste resin in a relatively short period of time. The volume of the waste resin and enrich the radionuclide in the residual carbon; on the other hand, the residual carbon after resin pyrolysis is also a microwave absorbing material, which can effectively improve the heating efficiency in the microwave pyrolysis process. In the present invention, the pyrolysis gas treatment system 3 can process the gas generated by pyrolysis, avoiding the emission of solid particles containing radionuclides and harmful gases.

Description

technical field [0001] The invention relates to the technical field of nuclear industry, in particular to a thermal cracking treatment device and method for radioactive waste resin. Background technique [0002] In the field of nuclear industry, ion exchange resins are widely used in the treatment of radioactive waste liquids. After such resins are no longer used due to various reasons such as expiry of service life and decommissioning, they need to be effectively treated and disposed of. The content of radionuclides in the radioactive waste resin is relatively high, and the radioactive waste resin is organic and flammable. It will be irradiated and degraded after long-term storage, producing H 2 、CH 4 、C 2 h 4 , NH 3 There are high safety risks such as flammable and explosive gases. [0003] Due to the high content of radionuclides in the radioactive waste resin, it is necessary to consider the safety of the operation when processing it. At present, for the treatment ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C10B53/07G21F9/30G21F9/32G21F9/36
CPCC10B53/07G21F9/30G21F9/304G21F9/32G21F9/36Y02P20/143
Inventor 刘艳牟涛张灏习成成桑培伦王志军胥静
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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