CN115159917B - Formula and method for curing and treating radioactive waste resin by cement - Google Patents
Formula and method for curing and treating radioactive waste resin by cement Download PDFInfo
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- CN115159917B CN115159917B CN202210784457.0A CN202210784457A CN115159917B CN 115159917 B CN115159917 B CN 115159917B CN 202210784457 A CN202210784457 A CN 202210784457A CN 115159917 B CN115159917 B CN 115159917B
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/02—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
- C04B28/04—Portland cements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/304—Cement or cement-like matrix
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00017—Aspects relating to the protection of the environment
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00025—Aspects relating to the protection of the health, e.g. materials containing special additives to afford skin protection
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/20—Resistance against chemical, physical or biological attack
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/20—Resistance against chemical, physical or biological attack
- C04B2111/27—Water resistance, i.e. waterproof or water-repellent materials
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2201/00—Mortars, concrete or artificial stone characterised by specific physical values
- C04B2201/50—Mortars, concrete or artificial stone characterised by specific physical values for the mechanical strength
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
- Y02W30/91—Use of waste materials as fillers for mortars or concrete
Abstract
The invention discloses a formula of cement curing treatment radioactive waste resin, which comprises the following components in parts by weight: 1 part of ordinary Portland cement, 0.25 to 0.35 part of radioactive waste resin, 0.3 to 0.4 part of water, 0.002 to 0.005 part of water reducer, 0.05 to 0.08 part of waterproof agent, 0.05 to 0.08 part of admixture and 0.1 to 0.2 part of fly ash. The present disclosure also discloses a method for curing and treating radioactive waste resin by cement. The cement mortar provided by the invention has proper fluidity and setting time, can solve the problems of difficult discharging after stirring and difficult cleaning and decontamination, and is especially suitable for the external stirring cement curing process of radioactive waste resin barrels.
Description
Technical Field
The invention belongs to the technical field of radioactive waste solidification treatment, and particularly relates to a formula and a method for solidifying and treating radioactive waste resin by cement.
Background
The cement solidification is a radioactive waste resin solidification treatment technology widely used at home and abroad, utilizes the material containing and adsorbing effects of cement to solidify radionuclides, has the advantages of simple process, mature technology, small equipment consumption, low energy consumption, safety, reliability and the like, has stronger compressive strength and self-shielding capacity, better radiation resistance and heat resistance, can meet the near-surface treatment requirement, and is an economic and reliable choice of nuclear chemical facilities and nuclear power plants in the aspect of radioactive waste resin treatment.
The external stirring cement curing process is a common cement curing treatment mode, has the advantages of high filling rate, high treatment capacity, convenient maintenance and the like, but has higher requirements on the initial fluidity and 30 minutes fluidity of cement mortar obtained in the cement curing process, the existing formula is difficult to meet the requirements of external stirring cement curing, the problems of difficult bleeding of a cement curing body and discharging and difficult cleaning and decontamination after stirring are easily caused, and the volume inclusion rate of radioactive waste resin is lower, and the radionuclide leaching rate level of the cement curing body is higher.
Disclosure of Invention
The invention aims to solve the technical problems of the prior art, and provides a formula and a method for curing radioactive waste resin by cement, and the prepared cement mortar has proper fluidity and setting time, can solve the problems of difficult discharging after stirring, difficult cleaning and decontamination and the like, and is particularly suitable for the process for curing the cement by stirring the radioactive waste resin outside a barrel.
The technical scheme for solving the technical problems is as follows:
according to one aspect of the present invention, there is provided a formulation for cement curing treatment of radioactive waste resin, comprising the following components in parts by weight:
1 part of ordinary Portland cement;
0.25-0.35 part of radioactive waste resin;
0.3 to 0.4 part of water;
0.002-0.005 part of water reducer;
0.05 to 0.08 portion of waterproof agent;
0.05 to 0.08 portion of admixture;
0.1 to 0.2 portion of fly ash.
Preferably, the model of the ordinary Portland cement is P.O42.5; the water is desalted water; the water reducing agent is a polycarboxylic acid compound; the waterproof agent is a modified siliceous material; the admixture is metakaolin material.
Preferably, the polycarboxylic acid compound is one or a combination of two of polyester polycarboxylic acid and polyether polycarboxylic acid; the modified siliceous material is one or the combination of two of silicon powder and siliceous waterproof agent.
Preferably, the volume ratio of the strong-alkaline negative resin to the strong-acid positive resin in the radioactive waste resin is 1:5-5:1.
Preferably, the particle size of the radioactive resin ranges from 0.40 to 1.20mm.
Preferably, the wet apparent density of the radioactive resin is in the range of 0.65 to 0.85g/mL, and the moisture content of the radioactive resin on a wet basis is 45 to 55%.
According to another aspect of the present invention, there is provided a method for curing a radioactive waste resin with cement, comprising:
s11, respectively weighing the water reducer, the waterproof agent, the admixture and the fly ash according to the formula, uniformly mixing and preparing into an additive;
s12, respectively weighing ordinary Portland cement, radioactive waste resin and water according to the formula, firstly adding the water and the radioactive waste resin into a stirring device for stirring, then adding the ordinary Portland cement and the additive in batches, and uniformly stirring to obtain cement mortar;
s13, filling the cement mortar into a steel drum, sealing the steel drum, curing and solidifying to obtain the cement solidified body of the radioactive waste resin.
Preferably, the method further comprises:
the radioactive waste resin is dehydrated and pretreated before being weighed
The formula and the method for the cement curing treatment of the radioactive waste resin can ensure that cement mortar has proper fluidity and setting time by adding proper amount of water reducer, waterproofing agent, admixture and fly ash, specifically, the cement mortar has the initial fluidity of 250-350 mm,30 min fluidity of 220-340 mm, initial setting time of 31-49 h, complete final setting time of 32-58 h and complete meeting the application requirement of stirring outside a barrel, and the method is particularly suitable for the cement curing process of stirring outside the barrel of the radioactive waste resin, can solve the problems of difficult discharging after stirring and difficult cleaning and decontamination in the prior art, can meet the requirements of GB14569.1-2011 on low and horizontal radioactive waste curing body performance requirement-cement curing body, can reduce the level of the nuclide leaching rate of a cement curing body by 1-2 nuclide levels compared with the standard requirement, and can reduce the cumulative leaching fraction of the cement curing body by more than 50% compared with the standard requirement of 42 days. In addition, the formula has good compatibility to the components in the radioactive waste resin, the fluctuation range of the volume ratio (the yin-yang ratio) of the strong alkaline negative resin to the strong acid positive resin in the radioactive waste resin is 1:5-5:1, the influence of the fluctuation of the material components of the radioactive waste resin, the errors of a metering system and the like can be overcome, the fluidity and the setting time of cement mortar are ensured to be in a reasonable range, the situations that the resin floats up and is unevenly distributed in a cement curing body are avoided, and the formula is applicable to the cement curing of most radioactive waste resins. In addition, the raw materials of the formula are easy to obtain, and especially the common silicate cement can be produced and supplied locally, so that the cost is greatly reduced; the formula has high volume-to-cure rate of 35% -40% on radioactive waste resin, and is higher than or at least not lower than the volume-to-cure rate of the existing out-of-barrel stirring cement curing formula which is generally about 30%.
Drawings
FIG. 1 is a formulation of a cement curing treatment radioactive waste resin in an embodiment of the present invention;
fig. 2 is a flow chart of a method of curing radioactive waste resin with cement in an embodiment of the present invention.
Detailed Description
In order that those skilled in the art will better understand the technical solutions of the present invention, a clear and complete description of the technical solutions of the present invention will be provided below with reference to the accompanying drawings, and it is apparent that the described embodiments are some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
Example 1
As shown in fig. 1, this example discloses a formulation of cement curing treatment radioactive waste resin, which comprises the following components in parts by weight:
1 part of ordinary Portland cement;
0.25-0.35 part of radioactive waste resin;
0.3 to 0.4 part of water;
0.002-0.005 part of water reducer;
0.05 to 0.08 portion of waterproof agent;
0.05 to 0.08 portion of admixture;
0.1 to 0.2 portion of fly ash.
Specifically, the model of the ordinary Portland cement is P.O42.5, various performance parameters of the ordinary Portland cement accord with the requirements of GB175-2007 general Portland cement, the cement is easy to produce, and the ordinary Portland cement can be directly produced and supplied by a local cement factory, so that the cost can be reduced;
the water is demineralized water, deionized water, tap water, etc., and is preferably demineralized water in this embodiment.
The water reducer is a polycarboxylic acid compound, and can be one or the combination of two of polyester type polycarboxylic acid and polyether type polycarboxylic acid.
The waterproof agent is a modified siliceous material, and can be one or a combination of more of silicon powder and organic silicon waterproof agent.
The admixture is metakaolin material, such as metakaolin.
The radioactive waste resin is a radioactive waste resin produced by a post-treatment plant in a nuclear facility, which may contain a strongly basic anion resin and/or a strongly acidic cation resin, and the fluctuation range of the volume ratio (yin-yang ratio) of the strongly basic anion resin to the strongly acidic cation resin is preferably 1:5 to an extent5:1, preferably 0.40-1.20 mm in particle size, preferably 0.65-0.85 g/mL in wet apparent density (wet resin bulk density), preferably 55% or less in moisture content of radioactive resin, and 45-55% in moisture content of radioactive resin, wherein the radionuclide mainly comprises 90 Sr、 137 Cr, and 60 Co。
the formula of the radioactive waste resin for cement curing treatment of the embodiment can enable cement mortar to have proper fluidity and setting time by adding proper amounts of water reducer, waterproofing agent, admixture and fly ash, specifically, the cement mortar has the initial fluidity of 275-340 mm,30 min fluidity of 240-340 mm, initial setting time of 31-49 h and complete final setting time of 32-58 h, can completely meet the application requirement of stirring outside a barrel, is particularly suitable for the cement curing process of stirring outside the radioactive waste resin barrel, can solve the problems of difficult discharging after stirring and difficult cleaning and decontamination in the prior art, can meet the requirements of GB14569.1-2011 on the performance requirement of horizontal radioactive waste curing body, namely cement curing body, can reduce the leaching rate level of the cement curing body nuclide by 1-2 orders of magnitude compared with the standard requirement in 42 days, and can reduce the cumulative leaching fraction of the cement curing body nuclide by more than 50% compared with the standard requirement in 42 days. In addition, the formula has good compatibility to the components in the radioactive waste resin, the fluctuation range of the volume ratio (the yin-yang ratio) of the strong alkaline negative resin to the strong acid positive resin in the radioactive waste resin is 1:5-5:1, the influence of the fluctuation of the material components of the radioactive waste resin, the errors of a metering system and the like can be overcome, the fluidity and the setting time of cement mortar are ensured to be in a reasonable range, the situations that the resin floats up and is unevenly distributed in a cement curing body are avoided, and the formula is applicable to the cement curing of most radioactive waste resins. In addition, the raw materials of the formula are easy to obtain, and especially the common silicate cement can be produced and supplied locally, so that the cost is greatly reduced; the formula has high volume-to-cure rate of 35% -40% on radioactive waste resin, and is higher than or at least not lower than the volume-to-cure rate of the existing out-of-barrel stirring cement curing formula which is generally about 30%.
Example 2
As shown in fig. 2, the present embodiment discloses a method for curing and treating radioactive waste resin by cement, comprising:
s11, respectively weighing a water reducing agent, a waterproof agent, a blending agent and fly ash according to the formula of the cement curing treatment radioactive waste resin in the embodiment 1, and uniformly mixing to prepare an additive;
s12, according to the formula of the cement curing treatment radioactive waste resin in the embodiment 1, respectively weighing ordinary Portland cement, radioactive waste resin and water, firstly adding the radioactive waste resin and the water into a stirring device (such as an external stirring mixer), starting the stirring device, stirring, adding the ordinary Portland cement and the additive in batches, and stirring for a period of time (such as 5-40 min) until the mixture is uniformly stirred to obtain cement mortar;
s13, discharging the cement mortar obtained in the step S12 into a steel drum, sealing the steel drum, curing and solidifying to obtain the cement solidified body of the radioactive waste resin. In this embodiment, the curing time is preferably 28 days or more to ensure structural stability of the cement cured body.
In some embodiments, the method further comprises: before the radioactive waste resin is weighed, the radioactive waste resin is dehydrated and pretreated so that the moisture content of the radioactive waste resin on a wet basis is controlled to be less than 55 percent, and can be controlled to be 45-55 percent generally. In practice, the radioactive waste resin may be dehydrated by a pump until the weight of the radioactive waste resin is no longer reduced and the dehydration is stopped.
Several sets of preparation examples are provided below to carry out verification tests on the method of curing the radioactive waste resin of the cement of this example, wherein the amounts of water reducing agent, water repellent, admixture, and fly ash are as shown in table 1, and the radioactive waste resin is replaced with a simulated waste resin formulated with the components shown in table 2.
Table 1 formulation raw materials dosage
TABLE 2 Components of simulation solutions for radioactive waste resins
Preparation example 1
As shown in table 1, 0.003 parts of polyether type polycarboxylic acid, 0.068 parts of a composition of silicon powder and a siliceous waterproof agent (wherein the mass ratio of silicon powder to siliceous waterproof agent=1:10), 0.06 parts of metakaolin and 0.14 parts of class II fly ash are respectively weighed according to parts by weight, and are uniformly mixed and stirred to prepare an additive;
as shown in table 2, the following is 5:1 (e.g., styrene-divinylbenzene copolymer having gel-crosslinked structure with quaternary ammonium group [ -N (CH) 3 ) 3 OH]With strongly acidic cation resins (e.g., styrene-divinylbenzene copolymer of gel-type cross-linked structure having sulfonic acid groups (-SO) thereon 3 H) Cation exchange resin of (a), and mixing to obtain an initial simulated waste resin, and adding non-radioactive CsCl crystals and non-radioactive SrCl respectively at a mass of 0.004% of the initial simulated waste resin 2 Crystalline and non-radioactive CoCl 2 The crystals are mixed and stirred uniformly to prepare the final simulated waste resin so as to simulate the radioactive waste resin;
as shown in table 1, 1 part of Portland cement P.O42.5, 0.32 part of simulated waste resin, 0.38 part of desalted water and 0.271 part of the prepared additive are weighed according to parts by weight, firstly, 0.32 part of simulated waste resin and 0.38 part of desalted water are added into a 400L external stirring mixer together, stirring is started, and then 1 part of Portland cement and 0.27 part of additive are added in batches in sequence and stirred for 10 minutes until stirring is uniform, so as to obtain cement mortar;
and (3) discharging the cement mortar in the out-of-barrel stirring mixer into a specially-made steel barrel which meets the requirements of cement curing treatment on the radioactive waste resin, sealing the steel barrel, curing the cement mortar after 28 days, and obtaining the cement cured body of the radioactive waste resin, wherein the curing volume capacity rate is 35 percent, which is higher than or at least not lower than the curing volume capacity rate of the conventional out-of-barrel stirring cement curing formula which is generally about 30 percent.
The cement mortars and cement cured products of preparation example 1 were subjected to performance tests according to the standards of GB14569.1, GB/T7023, GB 1346 and the like, and the results of the performance tests are shown in Table 3.
TABLE 3 Performance test results of PREPARATION EXAMPLE 1
As shown in Table 3, the performance indexes of the cement mortar and the cement solidified body meet the corresponding national standard requirements, and the requirements of the outside-barrel stirring cement solidification process on fluidity and setting time can be met.
Preparation example 2
As shown in table 1, 0.004 parts of polyether type polycarboxylic acid, 0.055 parts of a composition of silicon powder and siliceous waterproof agent (wherein the mass ratio of silicon powder to siliceous waterproof agent is=1:1), 0.065 parts of metakaolin and 0.127 parts of class I fly ash are respectively weighed according to parts by weight, and are mixed and stirred uniformly to prepare an additive;
as shown in table 2, the following is 1:5, respectively measuring the volume ratio of the strong basic anion resin (for example, styrene-divinylbenzene copolymer with gel cross-linked structure and quaternary ammonium group [ -N (CH) 3 ) 3 OH]With strongly acidic cation resins (e.g., styrene-divinylbenzene copolymer of gel-type cross-linked structure having sulfonic acid groups (-SO) thereon 3 H) Cation exchange resin of (a), and mixing to obtain an initial simulated waste resin, and adding non-radioactive CsCl crystals and non-radioactive SrCl respectively at a mass of 0.004% of the initial simulated waste resin 2 Crystalline and non-radioactive CoCl 2 The crystals are mixed and stirred uniformly to prepare simulated waste resin so as to simulate radioactive waste resin;
as shown in table 1, 1 part of Portland cement P.O42.5, 0.32 part of simulated waste resin, 0.35 part of desalted water and 0.251 part of the prepared additive are weighed according to parts by weight, firstly, 0.32 part of simulated waste resin and 0.35 part of desalted water are added into a 400L external stirring mixer together, stirring is started, and then 1 part of Portland cement and 0.25 part of additive are added in batches in sequence and stirred for 10 minutes until stirring is uniform, so as to obtain cement mortar;
and (3) discharging the cement mortar in the external stirring mixer into a specially-made steel drum which meets the requirements of the cement curing treatment on the radioactive waste resin, sealing the steel drum, curing the cement mortar after 28 days to obtain a cement cured body, wherein the curing volume packing rate is 40%, which is higher than or at least not lower than the curing volume packing rate of the conventional external stirring cement curing formula which is generally about 30%.
The cement mortars and cement cured products of preparation example 2 were subjected to performance tests according to the standards of GB14569.1, GB/T7023, GB 1346 and the like, and the results of the performance tests are shown in Table 4.
TABLE 4 Performance test results of PREPARATION EXAMPLE 2
As shown in Table 4, the performance indexes of the cement mortar and the cement solidified body meet the corresponding national standard requirements, and the requirements of the outside-barrel stirring cement solidification process on fluidity and setting time can be met.
Preparation example 3
As shown in table 1, 0.004 parts of polyester type polycarboxylic acid, 0.075 parts of a composition of silicon powder and a siliceous waterproof agent (wherein the mass ratio of silicon powder to siliceous waterproof agent is=1:8), 0.075 parts of metakaolin and 0.166 parts of class I fly ash are respectively weighed according to parts by weight, and are mixed and stirred uniformly to prepare an additive;
as shown in table 2, the following is 1:2.5 volume ratio of strongly basic anion resin (e.g., styrene-divinylbenzene copolymer having gel-crosslinked structure with quaternary ammonium group [ -N (CH) 3 ) 3 OH]With strongly acidic cation resins (e.g., styrene-divinylbenzene copolymer of gel-type cross-linked structure having sulfonic acid groups (-SO) thereon 3 H) Cation exchange resin of (a), and mixing to obtain an initial simulated waste resin, and adding non-radioactive CsCl crystals and non-radioactive SrCl respectively at a mass of 0.004% of the initial simulated waste resin 2 Crystalline and non-radioactive CoCl 2 The crystals are mixed and stirred uniformly to prepare simulated waste resin so as to simulate radioactive waste resin;
as shown in table 1, 1 part of Portland cement P.O42.5, 0.35 part of simulated waste resin, 0.34 part of desalted water and 0.32 part of the prepared additive are weighed according to parts by weight, firstly, 0.35 part of simulated waste resin and 0.34 part of desalted water are added into a 400L external stirring mixer together, stirring is started, and then 1 part of Portland cement and 0.32 part of additive are added in batches in sequence and stirred for 10 minutes until stirring is uniform, so as to obtain cement mortar;
and (3) discharging the cement mortar in the external stirring mixer into a specially-made steel drum which meets the requirements of the cement curing treatment on the radioactive waste resin, sealing the steel drum, curing the cement mortar after 28 days to obtain a cement cured body, wherein the curing volume packing rate is 40%, which is higher than or at least not lower than the curing volume packing rate of the conventional external stirring cement curing formula which is generally about 30%.
The cement mortars and cement cured products of preparation example 3 were subjected to performance tests according to the standards of GB14569.1, GB/T7023, GB 1346 and the like, and the results of the performance tests are shown in Table 5.
TABLE 5 Performance test results of PREPARATION EXAMPLE 3
As shown in Table 5, the performance indexes of the cement mortar and the cement solidified body meet the corresponding national standard requirements, and the requirements of the outside-barrel stirring cement solidification process on fluidity and setting time can be met.
Preparation example 4
As shown in table 1, 0.005 parts of polyester polycarboxylic acid, 0.08 parts of a composition of silicon powder and a siliceous waterproof agent (wherein the mass ratio of silicon powder to siliceous waterproof agent=1:2), 0.08 parts of metakaolin and 0.187 parts of class II fly ash are respectively weighed, mixed and stirred uniformly to prepare an additive;
the strongly basic anionic resin (e.g. styrene-divinylbenzene copolymer with gel-crosslinked structure having quaternary ammonium groups [ -N (CH) 3 ) 3 OH]With strongly acidic cation resins (e.g., styrene-divinylbenzene copolymer of gel-type cross-linked structure having sulfonic acid groups (-SO) thereon 3 H) Is added) and the dehydration is stopped until the weight is no longer reduced, as shown in table 2, at 2.5:1 to obtain initial simulated waste resin, and adding non-radioactive CsCl crystal and non-radioactive SrCl according to 0.004% of the initial simulated waste resin mass 2 Crystalline and non-radioactive CoCl 2 The crystals are mixed and stirred uniformly to prepare simulated waste resin so as to simulate radioactive waste resin;
as shown in table 1, 1 part of Portland cement P.O42.5, 0.34 part of simulated waste resin, 0.32 part of desalted water and 0.352 part of the prepared additive are weighed according to parts by weight, firstly, 0.34 part of simulated waste resin and 0.32 part of desalted water are added into a 400L external stirring mixer together, stirring is started, and then 1 part of Portland cement and 0.35 part of additive are added in batches in sequence and stirred for 10 minutes until stirring is uniform, so as to obtain cement mortar;
and (3) discharging the cement mortar in the external stirring mixer into a specially-made steel drum which meets the requirements of the cement curing treatment on the radioactive waste resin, sealing the steel drum, curing the cement mortar after 28 days to obtain a cement cured body, wherein the curing volume packing rate is 40%, which is higher than or at least not lower than the curing volume packing rate of the conventional external stirring cement curing formula which is generally about 30%.
The cement mortars and cement cured products of preparation example 4 were subjected to performance tests according to the standards of GB14569.1, GB/T7023, GB 1346 and the like, and the results of the performance tests are shown in Table 6.
TABLE 6 Performance test results of PREPARATION EXAMPLE 4
As shown in Table 6, the performance indexes of the cement mortar and the cement solidified body meet the corresponding national standard requirements, and the requirements of the outside-barrel stirring cement solidification process on fluidity and setting time can be met.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (5)
1. The formula of the cement curing treatment radioactive waste resin is characterized by comprising the following components in parts by weight:
1 part of ordinary Portland cement;
0.25-0.35 parts of radioactive waste resin;
0.3-0.4 parts of water;
0.002-0.005 part of water reducer;
0.05-0.08 parts of a waterproof agent;
0.05-0.08 part of admixture;
0.1-0.2 parts of fly ash;
the model of the ordinary Portland cement is P.O42.5, the water reducer is one or the combination of two of polyester type polycarboxylic acid and polyether type polycarboxylic acid, the water-proofing agent is the combination of silica powder and siliceous water-proofing agent, the admixture is metakaolin,
the volume ratio of the strong alkaline negative resin to the strong acid positive resin in the radioactive waste resin is 1:5-5:1, the wet apparent density range of the radioactive resin is 0.65-0.85 g/mL, and the wet base water content of the radioactive resin is 45-55%.
2. The formulation for curing a radioactive waste resin of claim 1, wherein the water is demineralized water.
3. The formulation for curing and treating radioactive waste resin of claim 1, wherein the radioactive resin has a particle size ranging from 0.40 mm to 1.20mm.
4. A method for curing and treating radioactive waste resin by cement, comprising:
s11, respectively weighing a water reducing agent, a waterproof agent, a blending agent and fly ash according to the formula of any one of claims 1-3, and uniformly mixing to prepare an additive;
s12, respectively weighing ordinary Portland cement, radioactive waste resin and water according to the formula of any one of claims 1-3, firstly adding the water and the radioactive waste resin into a stirring device together for stirring, then adding the ordinary Portland cement and the additive in batches, and uniformly stirring to obtain cement mortar;
s13, filling the cement mortar into a steel drum, sealing the steel drum, curing and solidifying to obtain the cement solidified body of the radioactive waste resin.
5. The method of curing a radioactive waste resin with cement according to claim 4, further comprising:
the radioactive waste resin is subjected to dehydration pretreatment before being weighed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210784457.0A CN115159917B (en) | 2022-07-05 | 2022-07-05 | Formula and method for curing and treating radioactive waste resin by cement |
Applications Claiming Priority (1)
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