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Method for solidifying spent radioactive resin by blending sulphoaluminate cement and admixtures

A technology of sulfoaluminate cement and radioactive waste resin, which is applied in radioactive purification, nuclear engineering, etc., can solve the problems of low containment capacity and high nuclide leaching rate of solidified body, and achieve low leaching rate, low cost and simple operation Effect

Inactive Publication Date: 2013-10-16
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At present, the curing formula of radioactive waste resin cement actually used in nuclear power plants has the disadvantages of low containment capacity and high nuclide leaching rate of solidified body.

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0014] The method for the solidification of radioactive waste resin by sulphoaluminate cement composite mixture is carried out according to the following steps:

[0015] (1) Mix 1440g of sulfoaluminate cement, 100g of zeolite, 200g of slag, 180g of silica fume, 80g of fly ash, and 2g of UNF-5 water reducing agent to make a mixture;

[0016] (2) Stir the mixed material, 1L mixed resin and 125mL water in a mixer for 3min to make a slurry;

[0017] (3) Transfer the slurry to a Φ50mm×50mm mold, put it in a curing box for curing for 7 days after smoothing, the curing temperature is 25±5°C, and the relative humidity is ≥90%.

[0018] The compressive strength of cured body 7d was determined to be 13.1 MPa.

Embodiment 2

[0020] The method for the solidification of radioactive waste resin by sulphoaluminate cement composite mixture is carried out according to the following steps:

[0021] (1) Mix 1470g of sulfoaluminate cement, 100g of zeolite, 200g of slag, 170g of silica fume, 60g of fly ash, and 2.4g of UNF-5 water reducer to make a mixture;

[0022] (2) Stir the mixed material, 1L mixed resin and 110mL water in a mixer for 3 minutes to make a slurry; place a fluidity test mold in the center of the cement mortar fluidity tester, and divide the mixed slurry in the mixer The two layers are quickly loaded into the fluidity test mold to measure the fluidity of the slurry;

[0023] (3) Transfer the slurry mixed in the mixer to a mold of Φ50mm×50mm, smooth it and put it in a curing box for curing for 7 days, the curing temperature is 25±5°C, and the relative humidity is ≥90%.

[0024] The compressive strength of cured body 7d was determined to be 12.6MPa. The fluidity of the slurry is 216mm.

Embodiment 3

[0026] The method for the solidification of radioactive waste resin by sulphoaluminate cement composite mixture is carried out according to the following steps:

[0027] (1) Mix 1440g of sulfoaluminate cement, 100g of zeolite, 200g of slag, 180g of silica fume, 80g of fly ash, and 2g of UNF-5 water reducing agent to make a mixture;

[0028] (2) The mixed material, 1L containing 4g Cs + The mixed resin and 125mL water were stirred in a mixer for 3min to make a slurry;

[0029] (3) Transfer the slurry to a Φ50mm×50mm mold, put it in a curing box for curing for 28 days after smoothing, the curing temperature is 25±5°C, and the relative humidity is ≥90%, and then carry out the nuclide leaching test. The leaching agent is 1.5L of deionized water at 25°C, samples were taken at 1, 3, 7, 10, 14, 21, 28, 35 and 42 days and replaced with new leaching agents.

[0030] Cs + The leaching rate and cumulative leaching fraction on day 42 were 8.4 × 10 -7 cm / d and 7.1×10 -5 cm.

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Abstract

The invention discloses a method for solidifying spent radioactive resin by blending sulphoaluminate cement and admixtures, and belongs to the technical field of radioactive waste cement solidification. The method comprises the following steps of: first uniformly belnding the sulphoaluminate cement, zeolite, slag, silica powder, fly ash and a UNF-5 water reducing agent to prepare a mixture; then stirring the mixture, the spent radioactive resin and water in a stirring machine to prepare slurry; and finally transferring the slurry into a mould, screeding the slurry and placing the mould into acuring box for curing. By the method, the slurry is endowed with proper fluidity in a solidification process, and the compression strength and nuclide leaching yield of a solidified waste body meet national standards.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste cement solidification, and in particular relates to a method for solidifying radioactive waste resin by sulphoaluminate cement compounding mixture. Background technique [0002] A large amount of radioactive ion exchange resins are produced during the operation, maintenance and waste liquid treatment of nuclear facilities. Waste resin contains a lot of water and is dispersible. It will produce explosive gas during radiolysis or pyrolysis. It must be cured in a suitable way to facilitate storage, transportation and disposal. Cement solidification technology is widely used in the solidification of medium and low-level radioactive waste due to its advantages of stable performance, simple equipment, easy operation, and low cost. At present, the curing formula of radioactive waste resin cement actually used in nuclear power plants has the disadvantages of low containment capacity and high nu...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/36C04B28/36
Inventor 王建龙孙奇娜李俊峰
Owner TSINGHUA UNIV