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Chemically bonded gelling material for curing radioactive waste resin and curing method thereof

A technology of radioactive waste resin and gelling material, which is applied in the direction of radioactive purification, solid waste management, climate sustainability, etc., can solve the problems of large volume increase ratio of solidified body, low containment capacity, and inability to condense, and achieve waste packaging Increased capacity, good fluidity, and small loss of compressive strength

Active Publication Date: 2017-04-26
深圳市航天新材科技有限公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] Cement solidification is currently the most commonly used solidification method for medium and low waste, but the current cement solidification formula has disadvantages such as low containment capacity, high nuclide leaching rate, large volume increase ratio of solidified body, and easy cracks.
When solidifying boron-containing waste resins produced by pressurized water reactor nuclear power plants, due to the presence of boron elements, the solidification time is prolonged or even unable to solidify, which reduces the solidification efficiency
In the waste resin curing formula currently used in nuclear power plants, the waste resin volume containment capacity is only 35%, the volume increase ratio of the cured body is large, and the final disposal cost is expensive

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0022] Blast furnace slag grinding to prepare slag powder, powder specific surface area 420kg / m 3 . The percentage of each component in the composite mineral activator is: 56% SiO 2 , 28%Na 2 O, 8% CaO, 5% Na 2 SO 4 , 3%Na 2 CO 3 . The percentages of each component in the adsorbent are: 50% of sodium bentonite and 50% of zeolite. Take 70 parts by weight of slag powder, 15 parts by weight of composite mineral activator, and 15 parts by weight of adsorbent and mix them uniformly to prepare a chemically bonded gelling material. Then 1480g of chemically bonded gelling material and 1L of simulated radioactive waste resin plus 285g of water were stirred in a stirring pot for 7 minutes, and then moved into a mold of φ50×50mm to prepare a cured body. Put the test mold into the curing box for curing. The curing temperature is 20±1°C and the relative humidity is ≥90%. The strength is 14.6MPa; the cured body has no cracks on the surface after soaking for 90d, and the compressive...

Embodiment 2

[0024] 100% blast furnace slag, ground to prepare slag powder, powder specific surface area 420kg / m 3 . The percentage of each component in the composite mineral activator is: 56% SiO 2 , 28%Na 2 O, 8% CaO, 5% Na 2 SO 4 , 3%Na 2 CO 3 . The percentages of each component in the adsorbent are: 40% of sodium bentonite and 60% of kaolin. Take 66 parts by weight of slag powder, 18 parts by weight of composite mineral activator, and 16 parts by weight of adsorbent and mix them uniformly to prepare a chemically bonded gelling material. Then 1480g of chemically bonded gelling material and 1L of simulated radioactive waste resin plus 320g of water were stirred in a stirring pot for 7 minutes, and then moved into a mold of φ50×50mm to prepare a cured body. The waste holding capacity of the cured body was 61%. Put the test mold into the curing box for curing. The curing temperature is 20±1°C and the relative humidity is ≥90%. The strength is 17.5MPa; after soaking for 90 days, th...

Embodiment 3

[0026] 85% blast furnace slag, 15% fly ash, grind together to prepare slag powder, powder specific surface area 450kg / m 3 . The percentage of each component in the composite mineral activator is: 35% SiO 2 , 19%Na 2 O, 46% CaO. The percentages of each component in the adsorbent are: 50% of sodium bentonite and 50% of zeolite. Take 70 parts by weight of slag powder, 15 parts by weight of composite mineral activator, and 15 parts by weight of adsorbent and mix them uniformly to prepare a chemically bonded gelling material. Then 1350g of chemically bonded gelling material and 1L of simulated radioactive waste resin plus 280g of water were stirred in a stirring pot for 7 minutes, and then moved into a mold of φ50×50mm to prepare a cured body. The waste holding capacity of the cured body was 65%. Put the test mold into the curing box for curing. The curing temperature is 20±1°C and the relative humidity is ≥90%. The strength is 16.0MPa; after soaking for 90 days, the cured bod...

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Abstract

A method for solidification of radioactive waste resin using a chemically bonded cementitious material. The method involves preparing a chemically bonded cementitious material by means of uniformly mixing aluminosilicate-containing slag, a compound mineral activator, and a sorbent. The chemically bonded cementitious material is then mixed with radioactive waste resin and added water and stirred for 7 minutes in an agitation vessel, then transferred to a mold for curing. When using the present method to solidify radioactive waste resin, the water content of saturated waste resin is between 42% and 50%, the saturated waste resin content of the solidified form is as high as 60%, the solid form fluidity is between 140mm and 210mm, setting time is terminable within 12 hours, and the initial setting period is sure to be suitable for performing solidification operations. After curing for 28 days, compressive strength exceeds 10Mpa, freeze thaw cycle tests exceed ten times, and after a 90 day immersion test, the surface of the solid form shows no fissures, and loss of compressive strength is below 10%.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste resin curing, and in particular relates to a chemically bonded gelling material for curing radioactive waste resin and a curing method thereof. Background technique [0002] Ion exchange resins are often used in chemical separation, purification, preparation, etc., and are widely used in nuclear industry factories and mines, isotope preparation, and radiochemical research, especially in nuclear power plants. . When the radioactive level of the loaded nuclide is too high or the exchange capacity is saturated, the resin in the equipment needs to be replaced regularly, which will generate a large amount of radioactive waste resin, and the waste resin after unloading needs to be cured before it can be disposed of. [0003] The cement solidification method is currently the most commonly used solidification method for medium and low waste, but the current cement solidification formula has dis...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C04B28/08C04B18/20
CPCC04B18/20G21F9/28Y02W30/91
Inventor 翁履谦曹海琳郭悦李绍彬李国学
Owner 深圳市航天新材科技有限公司
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