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Method for curing radioactive waste resin by NaAlO2 coagulant cement

A technology for solidifying radioactive waste resin and cement, which is applied in the field of solidifying radioactive waste resin with NaAlO2 coagulant cement, can solve the problems of prolonged slurry coagulation time, large volume increase ratio of solidified body, and expensive disposal costs, and achieves improved waste packaging. Capacity and compressive strength, effect of shortening setting time

Inactive Publication Date: 2015-06-10
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Cement solidification technology is the main solidification method of radioactive waste resin, but the waste containment capacity is low
Especially when solidifying the boron-containing waste resin produced by the pressurized water reactor nuclear power plant, the increase in the containment capacity increases the amount of boron contained in the solidified body per unit volume, resulting in a sharp extension of the coagulation time of the slurry or even failure to coagulate
At present, the solidified body of C1 concrete barrels produced by domestic pressurized water reactor nuclear power plants has a volume containment capacity of about 35% of the waste resin, and the volume increase ratio of the solidified body is large, so the final disposal cost is expensive

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0013] With 1505g sulfoaluminate cement, 95g composite mineral additive (zeolite: slag: silica fume: fly ash=5:10:9:4), 15g NaAlO 2 , 3g NaOH, mix evenly, stir with 1L simulated radioactive waste resin in the stirring pot for 3 minutes, fill the stirred slurry once with the coagulation time measurement test mold, vibrate several times to scrape the surface and put it into the curing box, the curing temperature is 20±1℃, relative humidity ≥90%. Measure the initial setting time after curing until 30 minutes after the start of stirring. After the initial setting time is measured, turn the setting time test mold over to continue curing, and measure the final setting time. The measured initial and final setting times were 4.7h and 19.0h, respectively.

Embodiment 2

[0015] With 1505g sulfoaluminate cement, 95g composite mineral additive (zeolite: slag: silica fume: fly ash=5:10:9:4), 15g NaAlO 2 , 3g NaOH, mix evenly, stir with 1L simulated radioactive waste resin in a stirring pot for 3 minutes, move to a Φ50mm×50mm mold, prepare a cured body, calculate the total volume of the cured body and use this to calculate the volume inclusion capacity of the waste resin in the cured body , to obtain a value of 65% of the containment capacity.

Embodiment 3

[0017] With 1505g sulfoaluminate cement, 95g composite mineral additive (zeolite: slag: silica fume: fly ash=5:10:9:4), 15g NaAlO 2 , 3g NaOH, mix evenly, stir with 1L simulated radioactive waste resin in a stirring pot for 3 minutes, move to a Φ50mm×50mm mold, and cure. The curing temperature is 25±5°C and the relative humidity is ≥90%. After curing for 48 hours, remove the mold, and after curing for 7 days, the upper and lower surfaces are properly polished with sandpaper to keep the upper and lower surfaces parallel, and then the unconfined compressive strength is measured on a pressure testing machine. The measured 7d compressive strength is 14.5MPa.

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Abstract

The invention discloses a method for curing a radioactive waste resin by NaAlO2 coagulant cement, and belongs to the technical field of radioactive waste resin cement curing. The method comprises the following steps of mixing sulfoaluminate cement, a composite mineral additive, NaAlO2 and NaOH well, stirring the mixture and a radioactive waste resin in a stirring kettle, transferring the mixture obtained by the previous step into a mold and maintaining for curing. The method is utilized for curing a radioactive waste resin, improves a capacity and compressive strength of cured waste, and shortens coagulation time.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste resin cement solidification, in particular to a method using NaAlO 2 A method for solidifying radioactive waste resin with coagulant cement. Background technique [0002] In nuclear power plants, ion exchange technology is widely used in auxiliary systems of the primary and secondary circuits and radioactive waste liquid treatment systems. Due to the high radioactive level of the loaded nuclides or the saturation of the exchange capacity, the resin in the equipment needs to be replaced regularly. Waste resin must be cured before final disposal. Cement solidification technology is the main solidification method of radioactive waste resin, but the waste containment capacity is low. Especially when solidifying the boron-containing waste resin produced by the pressurized water reactor nuclear power plant, the increase in the containment capacity will increase the amount of boron contained ...

Claims

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Application Information

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