CN102276231B - Method for curing radioactive waste resin by NaAlO2 coagulant cement - Google Patents
Method for curing radioactive waste resin by NaAlO2 coagulant cement Download PDFInfo
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- CN102276231B CN102276231B CN201110141157.2A CN201110141157A CN102276231B CN 102276231 B CN102276231 B CN 102276231B CN 201110141157 A CN201110141157 A CN 201110141157A CN 102276231 B CN102276231 B CN 102276231B
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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
The invention belongs to radioactive spent resin cement solidification technical field, be specifically related to a kind of use NaAlO
2the method of setting accelerator cement solidification radioactive spent resin.
Background technology
In Nuclear power plants, ion exchange technique is widely used in one, the subsystem of secondary circuit and Liquid Radwaste Treatment, the reason such as the too high or exchange capacity of the nuclide emission level due to load is saturated, resin in equipment needs periodic replacement, just can carry out ultimate disposal after the spent resin of unloading has to pass through solidification.Cement solidification technology is the primary curing means of radioactive spent resin, but refuse containing amount is lower.When particularly solidifying the boracic spent resin that pressurized-water reactor nuclear power plant produces, the increase of containing amount makes the boron amount contained by unit volume cured body increase, and causes slurry sharply to extend time of coagulation and even cannot condense.The C1 concrete bucket cured body that current domestic pressurized-water reactor nuclear power plant produces, spent resin volume containing amount is about 35%, and cured body increase-volume ratio is large, ultimate disposal somewhat expensive.
Aluminosulfate cement is the cement series that China has independent intellectual property right, and the research for solidification of radwaste has been reported.Ettringite is one of main hydration products of aluminosulfate cement, there is [Al (OH) in its crystal
6]
3-octahedral structure, its nucleation needs certain degree of supersaturation, just can complete Crystallization Process.When having boron to exist in aquation system, calcium in boron and cement component reacts the lime borate generating and be slightly soluble in water, lime borate crystal accumulation cement clinker particles surface, hinders cement to contact with water, be unfavorable for the formation of ettringite, therefore delay the hydration reaction of cement.Aluminosulfate cement solidification is containing admixture NaAlO in the formula of boron resin
2, Al in liquid phase (OH) can be improved
4 -concentration, increase [Al (OH)
6]
3-generating rate, promote the generation of ettringite, thus reach short and gaze fixedly at.
Refuse kind handled by cement solidification technology and composition various, the impact for cement hydration process is complicated, the normal time of coagulation using setting accelerator to regulate cement.No. 200810097228.1 patents provide a kind of solidifying agent for solid castoff concrete, which use setting accelerator but and its concrete composition unexposed.The disclosed cement type used for the solidifying agent of municipal sewage plant drain sludge and river sludge of No. 200810036184.1 patents is aluminosulfate cement, and setting accelerator is lithium salts or lithium hydroxide.In the application of radwaste cement solidification, admixture setting accelerator can shorten time of coagulation, improve cured body performance.No. 201010269158.0 patent discloses a kind of solidifying agent solidifying containing borate radwaste, and the cement type of use is silicate cement or aluminosulfate cement, and setting accelerator is water glass.During the ordinary Portland cement such as Wang Ren, trass cement, high-alumina cement and zeolite cement solidification radioactive liquid waste, employ sodium metaaluminate and make setting accelerator, shorten the setting time (Study on Cement Solidification of pressurized-water reactor nuclear power plant radioactive liquid waste of slurry, radio-protective, 1982,2 (5): 352-360).
Summary of the invention
The object of the present invention is to provide a kind of use NaAlO
2the method of setting accelerator cement solidification radioactive spent resin.
A kind of use NaAlO
2the method of setting accelerator cement solidification radioactive spent resin, by aluminosulfate cement, composite minerals additive, NaAlO
2, NaOH mixes, in agitator kettle, stir 3min with radioactive spent resin, move in the mould of Φ 50mm × 50mm, maintenance 7d, curing temperature is 25 ± 5 DEG C, relative humidity>=90%.
Described composite minerals additive is the mixture of zeolite, slag, silicon ash and flyash, and zeolite, slag, silicon ash is 5: 10: 9: 4 with the mass ratio of flyash.
Described radioactive spent resin, aluminosulfate cement, composite minerals additive, NaAlO
2with the usage ratio of NaOH be: 1L: (1455 ~ 1674) g: (45 ~ 126) g: (8 ~ 16) g: (1 ~ 4) g.Wherein, composite minerals additive account for aluminosulfate cement and composite minerals additive total mass 3% ~ 7%, NaAlO
2be 6: 1 ~ 4: 1 with the volume mass ratio of NaOH.
Beneficial effect of the present invention: method solidification radioactive spent resin of the present invention, improves refuse containing amount and the ultimate compression strength of cured body, shorten time of coagulation.
Embodiment
With specific embodiment, the present invention will be further described below.
Following examples adopt hybrid resin to be simulated radioactive spent resins, and in hybrid resin, the volume ratio of yin and yang resin is 3: 2, and the Boron contents on negative resin is about 1.2mol/L (in B).
Embodiment 1
10: 9: 4), 15g NaAlO by 1505g aluminosulfate cement, 95g composite minerals additive (zeolite: slag: silicon ash: flyash=5:
2, 3g NaOH mixes, in agitator kettle, stir 3min with 1L simulated radioactive spent resins, once filled by the slurry be stirred and measure die trial time of coagulation, vibration puts into maintaining box after striking off surface for several times, curing temperature is 20 ± 1 DEG C, relative humidity>=90%.Maintenance measures the presetting period to when starting to stir rear 30min, and die trial upset time of coagulation is continued maintenance, measures final setting time after completing mensuration by the presetting period.The initial set recorded and final setting time are respectively 4.7h and 19.0h.
Embodiment 2
10: 9: 4), 15g NaAlO by 1505g aluminosulfate cement, 95g composite minerals additive (zeolite: slag: silicon ash: flyash=5:
2, 3g NaOH mixes, in agitator kettle, stir 3min with 1L simulated radioactive spent resins, move in the mould of Φ 50mm × 50mm, prepare cured body, calculate the cumulative volume of cured body and calculate spent resin volume containing amount in cured body with this, obtaining containing numerical quantity is 65%.
Embodiment 3
10: 9: 4), 15g NaAlO by 1505g aluminosulfate cement, 95g composite minerals additive (zeolite: slag: silicon ash: flyash=5:
2, 3g NaOH mixes, in agitator kettle, stir 3min with 1L simulated radioactive spent resins, move in the mould of Φ 50mm × 50mm, maintenance, curing temperature is 25 ± 5 DEG C, relative humidity>=90%.The demoulding after maintenance 48h, after maintenance 7d, suitably polishes its upper and lower surface sand paper, keeps upper and lower surface parallel, then in its unconfined compression strength of pressure test aircraft measurements.Recording 7d ultimate compression strength is 14.5MPa.
Embodiment 4
10: 9: 4), 14.2g NaAlO by 1505g aluminosulfate cement, 115g composite minerals additive (zeolite: slag: silicon ash: flyash=5:
2, 2.8g NaOH mixes, in agitator kettle, 3min is stirred with 1L simulated radioactive spent resins, use the time of coagulation measuring method identical with embodiment 1, the spent resin volume bag capacity calculation methods identical with embodiment 2, the cured body preparation method identical with embodiment 3 and 7d intensity test method, the final setting time obtained, containing amount and 7d ultimate compression strength numerical value are respectively 17.5h, 61% and 12.7MPa.
Embodiment 5
10: 9: 4), 14.2g NaAlO by 1515g aluminosulfate cement, 65g composite minerals additive (zeolite: slag: silicon ash: flyash=5:
2, 3g NaOH mixes, in agitator kettle, 3min is stirred with 1L simulated radioactive spent resins, use the time of coagulation measuring method identical with embodiment 1, the spent resin volume bag capacity calculation methods identical with embodiment 2, the cured body preparation method identical with embodiment 3 and 7d intensity test method, the final setting time obtained, containing amount and 7d ultimate compression strength numerical value are respectively 20.3h, 65% and 11.3MPa.
Claims (1)
1. one kind uses NaAlO
2the method of setting accelerator cement solidification radioactive spent resin, is characterized in that, by aluminosulfate cement, composite minerals additive, NaAlO
2, NaOH mixes, in agitator kettle, stir 3min with radioactive spent resin, move in the mould of Φ 50mm × 50mm, maintenance 7d, curing temperature is 25 ± 5 DEG C, relative humidity>=90%; Wherein radioactive spent resin, aluminosulfate cement, composite minerals additive, NaAlO
2with the usage ratio of NaOH be: 1L:(1455 ~ 1674) g:(45 ~ 126) g:(8 ~ 16) g:(1 ~ 4) g; Wherein composite minerals additive is the mixture of zeolite, slag, silicon ash and flyash, and zeolite, slag, silicon ash is 5:10:9:4 with the mass ratio of flyash.
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| CN201110141157.2A CN102276231B (en) | 2011-05-27 | 2011-05-27 | Method for curing radioactive waste resin by NaAlO2 coagulant cement |
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| CN201110141157.2A CN102276231B (en) | 2011-05-27 | 2011-05-27 | Method for curing radioactive waste resin by NaAlO2 coagulant cement |
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| CN102276231B true CN102276231B (en) | 2015-06-10 |
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Families Citing this family (5)
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|---|---|---|---|---|
| CN104291762B (en) * | 2014-09-24 | 2017-04-26 | 深圳市航天新材科技有限公司 | Chemically bonded cementing agent for curing radioactive spent resin and curing method of chemically bonded cementing agent |
| CN105130305B (en) * | 2015-08-25 | 2018-01-12 | 武汉理工大学 | A kind of AASC Solidified Form method of nuclear power station boracic spent resin |
| CN112691632A (en) * | 2021-01-22 | 2021-04-23 | 广西新广建新材料有限公司 | Alkali-free accelerator production system |
| CN114420334B (en) * | 2021-12-20 | 2023-06-27 | 燕山大学 | Method for treating radioactive waste resin to obtain high-stability waste bag |
| CN115159934A (en) * | 2022-07-14 | 2022-10-11 | 燕山大学 | Radioactive waste resin solidified body containing fibrous mineral mixed material and preparation method thereof |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000284092A (en) * | 1999-01-29 | 2000-10-13 | Toshiba Corp | Method and device for treating waste containing boron |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101456715B (en) * | 2008-12-25 | 2012-07-18 | 清华大学 | Boron-containing radioactive spent resin cement solidification method |
| CN101935200A (en) * | 2010-08-31 | 2011-01-05 | 清华大学 | Curing agent for curing radioactive wastes containing borate and method thereof |
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Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000284092A (en) * | 1999-01-29 | 2000-10-13 | Toshiba Corp | Method and device for treating waste containing boron |
Non-Patent Citations (2)
| Title |
|---|
| 李俊峰,赵刚,王建龙.放射性废树脂水泥固化中水化热的降低.《清华大学学报(自然科学版)》.2004,第44卷(第12期), * |
| 王韧,杨景田.压水堆核电站放射性废液的水泥固化研究.《辐射防护》.1982,第2卷(第5期), * |
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