CN111268976B - High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof - Google Patents
High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof Download PDFInfo
- Publication number
- CN111268976B CN111268976B CN202010209739.9A CN202010209739A CN111268976B CN 111268976 B CN111268976 B CN 111268976B CN 202010209739 A CN202010209739 A CN 202010209739A CN 111268976 B CN111268976 B CN 111268976B
- Authority
- CN
- China
- Prior art keywords
- cement
- waste liquid
- radioactive waste
- cgm
- fluidity
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Classifications
-
- 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
-
- 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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/16—Processing by fixation in stable solid media
- G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
- G21F9/165—Cement or cement-like matrix
-
- 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
-
- 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
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Inorganic Chemistry (AREA)
- Ceramic Engineering (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Curing Cements, Concrete, And Artificial Stone (AREA)
Abstract
The invention discloses a high-fluidity high-compactness middle-level radioactive waste liquid cement curing material and a preparation method thereof, belonging to the technical field of radioactive waste treatment. It includes: portland cement, horizontal radioactive waste liquid, CGM-A and an air entraining agent; wherein the mass ratio of the middle-level radioactive waste liquid to the portland cement is 1: (2-2.5); the mass of the Portland cement, the CGM-A and the air entraining agent is 1: (0.005-0.02): (0.0005-0.002). By adding CGM-A and an air entraining agent, the fluidity of cement mortar is improved, bleeding of a solidified body is reduced, and the leaching performance of the solidified body is improved.
Description
Technical Field
The invention relates to the technical field of radioactive waste treatment, in particular to a high-fluidity high-compactness middle-level radioactive waste liquid cement curing material and a preparation method thereof.
Background
In order to prevent the radioactive waste from causing harm to the human living environment, the radioactive waste is required to be solidified and stored for convenient transportation and storage, and then is stored in a radioactive solidified waste final disposal field for a long time so as to ensure that the radioactive nuclide is naturally decayed after the radioactive solidified waste is safely isolated from the environment for 300 years, and the radioactivity of the radionuclide is reduced to an acceptable level and is not harmful to the environment.
The cement solidification is a relatively safe solidification method, and the principle is that cement is used as an electrodeless gel material, the cement, radioactive wastes and other additives are mixed according to a certain proportion, and the hydration action of cement components is utilized to enable mixed slurry to form a cement test block with certain mechanical strength and durability, so that the purpose of waste solidification is realized.
Currently, the horizontal radioactive waste liquid in the cement solidification treatment is adopted, and a steel barrel is used as a packaging container. However, the following three problems still exist at present when the cement solidification of the medium radioactive waste liquid is used as engineering application: firstly, in engineering application, the discharge opening of the mixing stirrer is blocked due to the slurry fluidity deviation, and the cleaning water quantity of the mixing stirrer is increased due to the deposition of the slurry on the inner surface of the stirrer; secondly, the occurrence of a crater condition of a partially cured body caused by the existence of air holes in the cement test block; thirdly, the shrinkage ratio of the cured body is about 5 percent (volume ratio), and the crater, bleeding and salting-out conditions are increased, which directly affect the quality of the cured body.
Disclosure of Invention
The invention aims to provide a high-fluidity high-compactness middle-level radioactive waste liquid cement curing material and a preparation method thereof, and aims to solve the problems of low fluidity, more pores and bleeding of a cured body of the existing cement curing slurry.
The technical scheme for solving the technical problems is as follows:
a high-fluidity high-compactness middle-level radioactive waste liquid cement solidification material comprises: portland cement, horizontal radioactive waste liquid, CGM-A and an air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the silicate is 1: (2-2.5); the mass of the Portland cement, the CGM-A and the air entraining agent is 1: (0.005-0.02): (0.0005-0.002).
Further, in a preferred embodiment of the present invention, the portland cement includes p.o42.5 cement or P.O 52.5.5 cement.
Further, in the preferred embodiment of the present invention, the salt content of the above-mentioned middle level radioactive waste liquid is 120-240 g/L.
Further, in the preferred embodiment of the present invention, the CGM-A is CGM-270A, CGM-300A or CGM-320A.
Further, in a preferred embodiment of the present invention, the air-entraining agent is a fatty alcohol sulfonate air-entraining agent.
The curing method of the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following steps:
(1) the middle-level radioactive waste liquid, the CGM-A and the air entraining agent are stirred and mixed uniformly, and then are added into the Portland cement to be stirred and mixed uniformly, so that the cement mortar is prepared.
(2) And pouring the cement mortar into the test mold, and maintaining.
The invention has the following beneficial effects:
1. the curing material improves the fluidity of cement mortar by adding CGM-A into the silicate cement, plays a certain role in protecting a mixing stirrer and a feed opening in the process, prevents cement hardening in the mixing stirrer and prevents the feed opening from being blocked so as to reduce the amount of cleaning water. And an air entraining agent is added, so that the fluidity of the cement mortar can be increased, the bleeding phenomenon of a solidified body can be reduced, the collapse degree of cement can be effectively reduced, the fluidity of the cement mortar can reach more than 270mm, and no crater phenomenon is generated on the surface of the cement test block.
2. The CGM-A adopted by the invention is a high-strength non-shrinkage grouting material, which is prepared by taking a high-strength material as an aggregate, taking cement as a binding agent and taking substances with high flow state, micro-expansion, segregation prevention and the like as auxiliary materials. The high-performance modified Portland cement has excellent performance, is matched with Portland cement for use, and has the improvement effects of early strength, high self-fluidity, micro-expansibility, ageing resistance and the like on a curing material.
3. The fatty alcohol sulfonate air entraining agent adopted by the invention mainly comprises rosin resins, alkyl and alkyl aromatic hydrocarbon sulfuric acids, fatty alcohol sulfate and other components, can be used as a structure with high freeze-thaw resistance requirement, can enable cement to be better dispersed in water, can improve the fluidity of the cement under the condition of proper mixing amount, and can introduce a plurality of small bubbles which are uniformly distributed in the cement, thereby improving the freeze-thaw resistance of the cement.
Detailed Description
The principles and features of this invention are described below in conjunction with embodiments, which are included to explain the invention and not to limit the scope of the invention. The examples, in which specific conditions are not specified, were conducted under conventional conditions or conditions recommended by the manufacturer. The reagents or instruments used are not indicated by the manufacturer, and are all conventional products available commercially.
The invention relates to a horizontal shooting waste liquid cement curing material, which comprises the following components: portland cement, horizontal radioactive waste liquid, CGM-A and an air entraining agent; wherein the mass ratio of the middle-level radioactive waste liquid to the portland cement is 1: (2-2.5); the mass of the Portland cement, the CGM-A and the air entraining agent is 1: (0.005-0.02): (0.0005-0.002). Specifically, in the following examples, the mass ratio of the horizontal radioactive waste liquid, the portland cement, the CGM-a, and the air-entraining agent is 1000: (2000-2500): (10-50): (1-5).
In the following embodiment of the present invention, CGM-A is CGM-270A, but in other embodiments, CGM-300A or CGM-320A may be used instead.
Example 1:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O52.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2000: 10: 1; the salt content of the middle-level radioactive waste liquid is 120 g/L.
The method for curing the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following steps of:
(1) the middle-level radioactive waste liquid, the CGM-A and the air entraining agent are stirred and mixed uniformly, and then are added into the Portland cement to be stirred and mixed uniformly, so that the cement mortar is prepared.
(2) And pouring the cement mortar into the test mold, and curing for 28 days.
The cured slurry has the compressive strength of 17.3MPa, the fluidity of 250mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Example 2:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O42.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2200: 25: 3; the salt content of the middle-level radioactive waste liquid is 180 g/L.
The method for curing the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following steps of:
(1) the middle-level radioactive waste liquid, the CGM-A and the air entraining agent are stirred and mixed uniformly, and then are added into the Portland cement to be stirred and mixed uniformly, so that the cement mortar is prepared.
(2) And pouring the cement mortar into the test mold, and curing for 28 days.
The cured slurry has the compressive strength of 17.4MPa, the fluidity of 270mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Example 3:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O52.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2500: 50: 5; the salt content of the middle-level radioactive waste liquid is 240 g/L.
The method for curing the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following steps of:
(1) the middle-level radioactive waste liquid, the CGM-A and the air entraining agent are stirred and mixed uniformly, and then are added into the Portland cement to be stirred and mixed uniformly, so that the cement mortar is prepared.
(2) Pouring the cement mortar into the test mold, and curing for 30 days.
The cured slurry has the compressive strength of 17.5MPa, the fluidity of 260mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Example 4:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O42.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2060: 28.4: 2.884.
the salt content of the horizontal radioactive waste liquid in this example was identical to that of the horizontal radioactive waste liquid in example 2.
The curing method of the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material of the embodiment is consistent with that of the embodiment 2.
The cured slurry has the compressive strength of 18.2MPa, the fluidity of 265mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Example 5:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O42.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2060: 18.54: 1.854.
the salt content of the horizontal radioactive waste liquid in this example was identical to that of the horizontal radioactive waste liquid in example 2.
The curing method of the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material of the embodiment is consistent with that of the embodiment 2.
The cured slurry has the compressive strength of 16.8MPa, the fluidity of 270mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Example 6:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O42.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2060: 10.3: 1.03.
the salt content of the horizontal radioactive waste liquid in this example was identical to that of the horizontal radioactive waste liquid in example 2.
The method for curing the horizontal radioactive waste liquid cement curing material of the present example was the same as that of example 2.
The cured slurry has the compressive strength of 14.68MPa, the fluidity of 265mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Example 7:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O42.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2060: 41.2: 4.12.
the salt content of the horizontal radioactive waste liquid in this example was identical to that of the horizontal radioactive waste liquid in example 2.
The curing method of the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material of the embodiment is consistent with that of the embodiment 2.
The cured slurry has the compressive strength of 17.1MPa, the fluidity of 263mm, no air holes in the cured body, the shrinkage of the cured body of less than 0.5 percent and the bleeding disappearance within 24 hours.
Example 8:
the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material comprises the following components: P.O42.5 cement, horizontal radioactive waste liquid, CGM-A and fatty alcohol sulfonate air entraining agent; wherein the mass ratio of the horizontal radioactive waste liquid to the Portland cement to the CGM-A to the air entraining agent is 1000: 2060: 37.08: 3.708.
the salt content of the horizontal radioactive waste liquid in this example was identical to that of the horizontal radioactive waste liquid in example 2.
The curing method of the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material of the embodiment is consistent with that of the embodiment 2.
The cured slurry has the compressive strength of 17.2MPa, the fluidity of 257mm, no air holes in a cured body, the shrinkage of the cured body of less than 0.5 percent and 24-hour bleeding disappearance.
Analysis of results
1. Compressive strength of cured body 28d
The cement mortar obtained in example 2 and examples 4 to 8 was formed into a cylindrical (phi 50 mm) test block, and after curing for 28d in a standard curing box, the compressive strength was measured according to the requirements of GB 14569.1-2011 cement test block for the performance requirements of low and medium level radioactive waste solidified bodies, and the results are shown in table 1.
TABLE 1 compression Strength of Cement test pieces obtained in example 2 and examples 4 to 8
As can be seen from table 1: the compressive strength of all the samples is greater than 7MPa, and the requirement that the compressive strength of a cement solidified body sample is not less than 7MPa is met.
2. Impact resistance test
The cement test blocks obtained in examples 2 and 4 to 8 were subjected to a drop test from a 9 m high building onto a cement floor according to the requirements of GB 14569.1 to 2011, and the results are shown in table 2.
TABLE 2 impact resistance of cement test blocks obtained in example 2 and examples 4 to 8
The result shows that the test block prepared by the invention only has small cracks, and the test block does not completely break, and all the test blocks meet the national standard requirements.
3. Resistance to soaking
The test pieces obtained in example 2 and examples 4 to 8 were immersed in tap water for 90 days, and analyzed for the presence or absence of crystal precipitation in the water sample and the amount of loss of compressive strength after immersion, the results of which are shown in Table 3.
TABLE 3 anti-soak Properties of Cement test pieces obtained in example 2 and examples 4-8
Experimental results show that the highest strength loss of the cement solidified body test block after soaking is 14.4%, the average loss after soaking is 12.78%, the requirement that the strength loss of the solidified body after soaking is not more than 25% in national standard is met, and no crystal is precipitated in all tested soaked water samples.
4. Resistance to freeze-thaw.
The results of the freeze-thaw resistance test on the samples obtained in example 2 and examples 4 to 8 are shown in table 4.
TABLE 4 Freeze-thaw resistance of cement cured body test pieces prepared in example 2 and examples 4-8
Experimental results show that the maximum loss of the freeze-thaw resistance strength of the cement solidified body test block is 17.8%, the average loss is 14.85%, and the cement solidified body test block meets the requirement that the strength loss after being soaked in the national standard solidified body is not more than 25%.
5. Resistance to radiolysis
The test pieces prepared in example 2 and examples 4 to 8 were irradiated to a total dose of 2.2X 105Gy, and their compressive strength data after irradiation were measured as shown in Table 5.
TABLE 5 radiolysis resistance of cement cured test pieces obtained in example 2 and examples 4 to 8
The result shows that the compression strength of the solidified body after the cement test block is irradiated is not lost, and the national standard requirement is met.
6. Free liquid
After the cement mortars prepared in example 2 and examples 4 to 8 were cured for 7 days in a cement curing plant,
the results show that all cement samples have no free liquid on the surface, and the solidified body sample meets the national standard requirements.
7. Degree of fluidity
After preparing the cement mortar into a material for example 2 and examples 4-8, samples were taken on site to test the fluidity, and the fluidity data of the on site test are shown in Table 6.
TABLE 6 fluidity test of the cement mortars obtained in example 2 and examples 4 to 8
The result shows that the average value of the fluidity of the cement mixed mortar in the field test is 263mm, and the cement mixed mortar meets the national standard requirement.
8. Resistance to leaching
The test pieces prepared in example 2 and examples 4 to 8 were subjected to leaching experiments on the first 42 days, and the leaching amount of a single radionuclide on the 42 th day was measured, and the results are shown in table 7.
TABLE 7 nuclide leaching amounts of cement cured body test pieces obtained in example 2 and examples 4 to 8
The result shows that the leaching amounts of Sr, Cs and U radionuclides of the cement solidified body sample of the invention on day 42 are all lower than the national standard.
Examples of on-site tests
By adopting the high-fluidity high-compactness middle-level radioactive waste liquid curing material and the curing method thereof, a field experiment is carried out on a curing system in an out-of-drum stirring drum.
Wherein the addition amount of the middle-level radioactive waste liquid is 400L (2 batches), and the salt content is 180 g/L; the addition amount of the P.O42.5 cement is 424 kg; the addition amount of the CGM-270A is 3.816kg, and the addition amount of the air entraining agent of the fatty alcohol sulfonate is 0.3816 kg. The prepared cement mortar is prepared into a cylindrical (phi 50 mm) test block, and after the test block is maintained in a standard maintenance box for 28 days, the test block is subjected to performance tests according to the requirements of GB 14569.1-2011 cement test block requiring the performance of the low and medium horizontal radioactive waste solidified body, and the results are shown in Table 8.
TABLE 8 Performance results of cement cured body specimens of test examples
The results show that in the field test, the cement test block has complete appearance, moderate cement mortar fluidity in the stirring process, complete solidified body surface, no crack, no pore in the solidified body, less than 0.5 percent of solidified body shrinkage and no bleeding for 24 hours.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that fall within the spirit and principle of the present invention are intended to be included therein.
Claims (5)
1. A high-fluidity high-compactness middle-level radioactive waste liquid cement solidified material is characterized by comprising the following components in percentage by weight: portland cement, horizontal radioactive waste liquid, CGM-A and an air entraining agent; wherein the mass ratio of the middle-level radioactive waste liquid to the portland cement is 1: (2-2.5); the mass of the Portland cement, the CGM-A and the air entraining agent is 1: (0.005-0.02): (0.0005-0.002); the salt content of the middle-level radioactive waste liquid is 180 g/L.
2. The high flow, high density, medium level radioactive liquid cement solidification material according to claim 1, wherein the portland cement comprises p.o42.5 cement or p.o52.5 cement.
3. The high-fluidity high-compactness middle-level radioactive waste liquid cement solidification material according to claim 1, wherein the CGM-A is CGM-270A, CGM-300A or CGM-320A.
4. The high-fluidity high-compactness middle-level radioactive liquid waste cement curing material according to any one of claims 1 to 3, wherein the air entraining agent is a fatty alcohol sulfonate air entraining agent.
5. The method for curing the high-fluidity high-compactness middle-level radioactive waste liquid cement curing material according to any one of claims 1 to 4, is characterized by comprising the following steps of:
(1) firstly, uniformly stirring and mixing the middle-level radioactive waste liquid, the CGM-A and the air entraining agent, adding the mixture into Portland cement, and uniformly stirring and mixing to prepare cement mortar;
(2) and pouring the cement mortar into the test mold, and maintaining.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010209739.9A CN111268976B (en) | 2020-03-23 | 2020-03-23 | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010209739.9A CN111268976B (en) | 2020-03-23 | 2020-03-23 | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN111268976A CN111268976A (en) | 2020-06-12 |
| CN111268976B true CN111268976B (en) | 2022-03-08 |
Family
ID=71003855
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010209739.9A Active CN111268976B (en) | 2020-03-23 | 2020-03-23 | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111268976B (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114620983A (en) * | 2022-03-15 | 2022-06-14 | 中核四川环保工程有限责任公司 | High-compactness radioactive solid waste fixing body |
| CN114956717A (en) * | 2022-04-14 | 2022-08-30 | 浙江工业大学 | Application method of bone charcoal cement composite material for solidifying uranium-containing waste |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104529281A (en) * | 2014-12-12 | 2015-04-22 | 中核四川环保工程有限责任公司 | High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula |
-
2020
- 2020-03-23 CN CN202010209739.9A patent/CN111268976B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104529281A (en) * | 2014-12-12 | 2015-04-22 | 中核四川环保工程有限责任公司 | High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula |
Non-Patent Citations (1)
| Title |
|---|
| CGM设备灌浆料的性能和应用;仲晓林等;《工业建筑》;19931231;第32-36页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN111268976A (en) | 2020-06-12 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110845184B (en) | Recycled aggregate concrete and preparation method thereof | |
| WO2021012937A1 (en) | High-strength coral concrete and preparation method therefor | |
| CN111268976B (en) | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof | |
| FR2542223A1 (en) | PROCESS FOR INCORPORATING ION EXCHANGE RESINS IN SOLID MASS | |
| CN112479664A (en) | Boron-containing waste resin cement curing formula and curing method thereof | |
| CN112010595A (en) | Preparation method of high-strength semi-recycled coarse aggregate concrete | |
| CN111056789B (en) | Method for solidifying radioactive waste residues | |
| CN108298881A (en) | A kind of geological cement and its application for curing Radioactive chemical sludge | |
| KR20220016637A (en) | Concrete composition for revealing early strength | |
| RU2360313C1 (en) | Composition for cementation of liquid radioactive wastes | |
| Tang | Study of the possibilities of using Red Mud as an additive in concrete and grout mortar | |
| CN111524632A (en) | Magnesium-based cement curing substrate and method for treating low-medium radioactive nuclear waste | |
| CN107417236B (en) | Water-based capillary crystalline waterproof material | |
| CN115124298B (en) | High-strength recycled aggregate concrete prepared from waste stone powder and preparation method thereof | |
| WO2017214108A1 (en) | Strength enhancing admixtures for hydraulic cements | |
| FI20186089A1 (en) | Method for treating and solidifying liquid waste | |
| CN113061006A (en) | Boron-containing concentrated waste liquid cement curing formula and curing method thereof | |
| JP2015010010A (en) | Salt damage-resistant concrete | |
| CN113956018B (en) | Ceramsite concrete and preparation method thereof | |
| CN117986001B (en) | Curing agent based on multiple solid wastes and preparation method and application thereof | |
| Memis et al. | Some durability properties of alkali activated materials (AAM) produced with ceramic powder and micro calcite | |
| CN115678524B (en) | Casing anti-corrosion complexing agent and capsule for well cementation of oil and gas well, and preparation method and application thereof | |
| RU2100304C1 (en) | Raw mixture for extra strength and heavy concrete making | |
| RU2189366C2 (en) | Raw mixture for extra strength and heavy concrete preparing | |
| CN115806400B (en) | High-stability active slurry concrete admixture and preparation method thereof |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |