Cement solidification treatment method for radioactive waste

A radioactive waste, cement solidification technology, applied in radioactive purification, nuclear engineering and other directions, can solve the problems of low cost and material waste, and achieve the effect of reducing processing cost, improving technical reserves, and reducing waste disposal cost

Pending Publication Date: 2019-09-13
CHINA INST FOR RADIATION PROTECTION
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Such a situation leads to high cost of procurement and storage, and there is a problem of waste of materials

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0030] Embodiment 1: The cement curing treatment of radioactive boron-containing waste resin (1)

[0031] The composition and characteristics of radioactive boron-containing waste resin are: nuclear-grade anion-yang mixed resin (models GR-1-9NG, GR-2-0NG, GR-3-9NG, density 1.00g / cm 3 ), 137 Cs activity concentration is 5.34E+07Bq / L, 90 Sr activity concentration is 1.22E+05Bq / L, 60 Co activity concentration is 2.10E+07Bq / L.

[0032] The radioactive boron-containing waste resin adopts the following method steps to carry out cement solidification treatment.

[0033] (1) First add radioactive boron-containing waste resin into the waste bucket, then add the mixture of lime, Glenium C333, silica and alumina, stir for 15 minutes and then add cement (ordinary Portland cement) in 2 times, each time Adding time interval is 15min, continue stirring for 15min. The mass ratio of the mixture of cement, radioactive boron-containing waste resin, lime, Glenium C333, silica and alumina is ...

Embodiment 2

[0035] Embodiment 2: the cement solidification treatment of radioactive boron-containing waste resin (two)

[0036] The composition and characteristics of radioactive boron-containing waste resin are: nuclear-grade anion-yang mixed resin (models GR-1-9NG, GR-2-0NG, GR-3-9NG, density 1.00g / cm 3 ), 137 Cs activity concentration is 5.34E+07Bq / L, 90 Sr activity concentration is 1.22E+05Bq / L, 60 Co activity concentration is 2.10E+07Bq / L.

[0037] The radioactive boron-containing waste resin adopts the following method steps to carry out cement solidification treatment.

[0038] (1) First add radioactive boron-containing waste resin into the waste bin, then add the mixture of lime, Glenium C333, silica and alumina, stir for 10 minutes and then add cement (ordinary Portland cement) in 5 times, each time Adding time interval is 10min, continue stirring for 10min. The mass ratio of the mixture of cement, radioactive boron-containing waste resin, lime, Glenium C333, silica and alumin...

Embodiment 3

[0040] Embodiment 3: cement solidification treatment of radioactive boron-containing waste resin (three)

[0041] The composition and characteristics of radioactive boron-containing waste resin are: nuclear-grade anion-yang mixed resin (models GR-1-9NG, GR-2-0NG, GR-3-9NG, density 1.00g / cm 3 ), 137 Cs activity concentration is 5.34E+07Bq / L, 90 Sr activity concentration is 1.22E+05Bq / L, 60 Co activity concentration is 2.10E+07Bq / L.

[0042] The radioactive boron-containing waste resin adopts the following method steps to carry out cement solidification treatment.

[0043] (1) First add radioactive boron-containing waste resin to the waste bucket, then add the mixture of lime, Glenium C333, silica and alumina, stir for 13 minutes and then add cement (ordinary Portland cement) in 3 times, each time The addition time interval was 13 minutes, and the stirring was continued for 13 minutes. The mass ratio of the mixture of cement, radioactive boron-containing waste resin, lime, ...

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Abstract

Belonging to the technical field of radioactive waste treatment, the invention relates to a cement solidification treatment method for radioactive waste. The radioactive waste is radioactive boron-containing waste resin. The method comprises the steps of: (1) adding radioactive waste into a waste drum, then adding lime, an additive and a modifier, performing stirring for 10-15min, then adding cement and further conducting stirring for 10-15min; and (2) capping the stirring finished waste drum, then transferring the waste drum into a curing chamber for curing. The cement solidification treatment method for radioactive waste provided by the invention can increase the loading capacity of radioactive boron-containing waste resin and ensure that all the performance of waste cement solidified products meet the standard requirements under the premise of maintaining the original solidification equipment and technological operation basically unchanged directed at the problems existing in the practical application of Westinghouse solidification technology in the United States.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste treatment and relates to a cement solidification treatment method for radioactive waste. Background technique [0002] Cement solidification is a traditional radioactive waste stabilization treatment technology, which has technical advantages such as simple process, mature technology, low cost, and good stability of solidified waste. The basic principle of cement solidification is: use cement as the substrate for inorganic gel solidification, uniformly mix cement, radioactive waste and other materials in a certain proportion, and form a solidified body under suitable curing conditions, so as to realize the stabilization of waste. [0003] Since Ling Ao Phase II, a number of newly-built nuclear power units in China have introduced the cement solidification system for radioactive waste from Westinghouse. Compared with the original cement solidification treatment technology in China, this ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/30
CPCG21F9/304
Inventor 闫晓俊郭喜良安鸿翔郭霄斌高超柳兆峰刘建琴冯文东
Owner CHINA INST FOR RADIATION PROTECTION
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