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Method for solidifying radioactive waste resin by utilizing mixture of silicate and sulphate aluminium cement

A technology of sulfoaluminate cement and radioactive waste resin, which is applied in radioactive purification, nuclear engineering and other directions, can solve the problems of temperature cracks, slow release of hydration heat, and low resin package capacity, and achieves increased resin package capacity and hydration. The effect of reducing heat temperature rise

Inactive Publication Date: 2013-05-22
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Cement solidification is a commonly used method for the treatment of radioactive waste resins in China. Ordinary Portland cement solidification of radioactive waste resins has the defect of low resin containment capacity, but it has the characteristics of slow release of heat of hydration and good long-term stability; sulphoaluminate cement It can realize the efficient curing of radioactive waste resin, but there is a defect that the concentration of hydration heat release is easy to cause temperature cracks

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0011] Mix 42.5MPa ordinary Portland cement and 42.5MPa sulphoaluminate cement uniformly at a mass ratio of 3:1 to obtain a dry blend, and mix the dry blend, dehydrated radioactive waste resin and water at a mass ratio of 1:0.55:0.33 After uniformity, a cement slurry is obtained. The cement slurry is poured into a mold and cured for 28 days to obtain a cement solidified body.

[0012] The compressive strength of the cement solidified body is 10.3 MPa, and the highest temperature of the solidified body is 25 hours. No cracks appear on the surface of the cement cured body.

Embodiment 2

[0014] Mix 42.5MPa ordinary Portland cement and 42.5MPa sulphoaluminate cement uniformly at a mass ratio of 2:1 to obtain a dry mixture, and mix the dry mixture, dehydrated radioactive waste resin and water at a mass ratio of 1:0.55:0.33 After uniformity, a cement slurry is obtained. The cement slurry is poured into a mold and cured for 28 days to obtain a cement solidified body.

[0015] The compressive strength of the cement solidified body is 11.3MPa, and the highest temperature of the solidified body is 22 hours. No cracks appear on the surface of the cement cured body.

Embodiment 3

[0017] Mix 42.5MPa ordinary Portland cement and 42.5MPa sulphoaluminate cement uniformly at a mass ratio of 1:1 to obtain a dry mixture, and mix the dry mixture, dehydrated radioactive waste resin and water at a mass ratio of 1:0.60:0.30 After uniformity, a cement slurry is obtained. The cement slurry is poured into a mold and cured for 28 days to obtain a cement solidified body.

[0018] The compressive strength of the cement cured body is 12.8MPa, and the maximum temperature of the cured body is 20 hours. No cracks appear on the surface of the cement cured body.

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Abstract

The invention discloses a method for solidifying radioactive waste resin by utilizing mixture of silicate and sulphate aluminium cement in the technical field of radioactive waste processing. In the method, the mixture of common silicate cement and sulphate aluminium cement is used for solidifying the radioactive waste resin cement, the package size of waste resin cement solidification body is increased to 55 percent from 40 percent, the tensile strength of the solidification body can meet the requirements of national standard (more than 7MPa), and heat of hydration can be slowly released in the solidification process so as to prevent temperature crack of the solidification body.

Description

Technical field [0001] The invention belongs to the technical field of radioactive waste treatment and relates to a method for solidifying radioactive waste resin cement. Background technique [0002] A large amount of radioactive waste resin will be produced during the operation and decommissioning of nuclear power plants and nuclear facilities. The efficient treatment of radioactive waste resin is one of the problems that have long plagued the development of my country's nuclear industry. Cement curing is a commonly used method for domestic radioactive waste resin treatment. Ordinary Portland cement curing radioactive waste resin has the defect of low resin package capacity, but it has the characteristics of slow release of hydration heat and good long-term stability; sulphoaluminate cement It can realize the high-efficiency curing of radioactive waste resin, but there is a defect that concentrated hydration heat release is prone to temperature cracks. Summary of the invention...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/28G21F9/30G21F9/34C04B28/36
Inventor 李俊峰王建龙
Owner TSINGHUA UNIV
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