CN102276231A - 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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- CN102276231A CN102276231A CN2011101411572A CN201110141157A CN102276231A CN 102276231 A CN102276231 A CN 102276231A CN 2011101411572 A CN2011101411572 A CN 2011101411572A CN 201110141157 A CN201110141157 A CN 201110141157A CN 102276231 A CN102276231 A CN 102276231A
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- naalo
- spent resin
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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 the 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 and the Liquid Radwaste Treatment of secondary circuit, reason such as too high or exchange capacity is saturated owing to the nucleic radioactive level of load, resin in the equipment needs periodic replacement, and the spent resin of unloading must just can carry out ultimate disposal behind overcuring.The cement solidification technology is the main 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 increases the contained boron amount of unit volume cured body, causes slurry sharply to prolong time of coagulation even can't condense.The C1 concrete bucket cured body that present domestic pressurized-water reactor nuclear power plant produces, spent resin volume containing amount is about 35%, and cured body increase-volume ratio is big, ultimate disposal expense costliness.
Aluminosulfate cement is the cement series that China has independent intellectual property right, is used for the existing report of research of solidification of radwaste.Ettringite is one of main hydration products of aluminosulfate cement, has [Al (OH) in its crystal
6]
3-Octahedral structure, its nucleation needs certain degree of supersaturation, just can finish the crystallization process.When having boron to exist in the aquation system, calcium reaction in boron and the cement component generates the lime borate that is slightly soluble in water, and lime borate crystal accumulation cement clinker particle surface hinders cement and contacts with water, be unfavorable for that the ettringite crystalline forms, therefore delay the hydration reaction of cement.Aluminosulfate cement solidifies admixture NaAlO in the prescription that contains boron resin
2, can improve Al in the liquid phase (OH)
4 -Concentration, increase [Al (OH)
6]
3-Generating rate, promote the ettringite crystalline to generate, gaze fixedly at thereby reach short.
Handled refuse kind of cement solidification technology and composition are various, for the complexity that influences of cement hydration process, often use setting accelerator to regulate cement setting time.200810097228.1 number patent provides a kind of solidifying agent that is used for solid castoff concrete, has wherein used setting accelerator but and unexposed its concrete composition.200810036184.1 the cement kind that the solidifying agent that is used for municipal wastewater treatment plant draining mud and river course mud of number patent disclosure uses is aluminosulfate cement, setting accelerator is lithium salts or lithium hydroxide.In the application of radwaste cement solidification, the admixture setting accelerator can shorten time of coagulation, improve the cured body performance.201010269158.0 number patent disclosure a kind of solidifying agent that solidifies boracic hydrochlorate radwaste, the cement kind of using is silicate cement or aluminosulfate cement, setting accelerator is a water glass.Wang Ren etc. are during with ordinary Portland cement, trass cement, high-alumina cement and zeolite cement solidification radioactive liquid waste, used sodium metaaluminate to 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 is with aluminosulfate cement, composite minerals additive, NaAlO
2, NaOH mixes, and stirs 3min with radioactive spent resin in agitator kettle, move in the mould of Φ 50mm * 50mm, maintenance 7d, curing temperature is 25 ± 5 ℃, relative humidity 〉=90%.
Described composite minerals additive is the mixture of zeolite, slag, silicon ash and flyash, and zeolite, slag, silicon ash are 5: 10: 9 with the mass ratio of flyash: 4.
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, the composite minerals additive account for aluminosulfate cement and composite minerals additive total mass 3%~7%, NaAlO
2With the volume mass ratio of NaOH be 6: 1~4: 1.
Beneficial effect of the present invention: method of the present invention is solidified radioactive spent resin, has improved the refuse containing amount and the ultimate compression strength of cured body, has shortened time of coagulation.
Embodiment
The present invention will be further described with specific embodiment below.
It is the simulated emission spent resin that following examples adopt hybrid resin, and the volume ratio of yin and yang resin is 3: 2 in the hybrid resin, and the boron content on the negative resin is about 1.2mol/L (in B).
Embodiment 1
4), 15g NaAlO with 1505g aluminosulfate cement, 95g composite minerals additive (zeolite: slag: silicon ash: flyash=5: 10: 9:
2, 3g NaOH mixes, stir 3min with 1L simulated emission spent resin in agitator kettle, the slurry that stirs is once filled measured die trial time of coagulation, vibration is put into maintaining box after wipeing the surface off for several times, curing temperature is 20 ± 1 ℃, relative humidity 〉=90%.Maintenance is measured the presetting period when beginning to stir back 30min, and the presetting period is continued maintenance with die trial upset time of coagulation after finishing mensuration, measures final setting time.Initial set that records and final setting time are respectively 4.7h and 19.0h.
Embodiment 2
4), 15g NaAlO with 1505g aluminosulfate cement, 95g composite minerals additive (zeolite: slag: silicon ash: flyash=5: 10: 9:
2, 3g NaOH mixes, in agitator kettle, stir 3min with 1L simulated emission spent resin, move in the mould of Φ 50mm * 50mm, the preparation cured body, calculate the cumulative volume of cured body and calculate spent resin volume containing amount in the cured body with this, obtaining containing numerical quantity is 65%.
Embodiment 3
4), 15g NaAlO with 1505g aluminosulfate cement, 95g composite minerals additive (zeolite: slag: silicon ash: flyash=5: 10: 9:
2, 3g NaOH mixes, and stirs 3min with 1L simulated emission spent resin in agitator kettle, move in the mould of Φ 50mm * 50mm, maintenance, curing temperature is 25 ± 5 ℃, relative humidity 〉=90%.The demoulding behind the maintenance 48h behind the maintenance 7d, is suitably polished its upper and lower surface with 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
4), 14.2g NaAlO with 1505g aluminosulfate cement, 115g composite minerals additive (zeolite: slag: silicon ash: flyash=5: 10: 9:
2, 2.8g NaOH mixes, in agitator kettle, stir 3min with 1L simulated emission spent resin, use the time of coagulation measuring method identical with embodiment 1, the spent resin volume containing amount method of calculation identical with embodiment 2, cured body preparation method and the 7d intensity test method identical with embodiment 3, the final setting time that obtains, containing amount and 7d ultimate compression strength numerical value are respectively 17.5h, 61% and 12.7MPa.
Embodiment 5
4), 14.2g NaAlO with 1515g aluminosulfate cement, 65g composite minerals additive (zeolite: slag: silicon ash: flyash=5: 10: 9:
2, 3g NaOH mixes, in agitator kettle, stir 3min with 1L simulated emission spent resin, use the time of coagulation measuring method identical with embodiment 1, the spent resin volume containing amount method of calculation identical with embodiment 2, cured body preparation method and the 7d intensity test method identical with embodiment 3, the final setting time that obtains, containing amount and 7d ultimate compression strength numerical value are respectively 20.3h, 65% and 11.3MPa.
Claims (3)
1. one kind is used NaAlO
2The method of setting accelerator cement solidification radioactive spent resin is characterized in that, with aluminosulfate cement, composite minerals additive, NaAlO
2, NaOH mixes, and stirs 3min with radioactive spent resin in agitator kettle, move in the mould of Φ 50mm * 50mm, maintenance 7d, curing temperature is 25+5 ℃, relative humidity 〉=90%.
2. according to the described a kind of use NaAlO of claim 1
2The method of setting accelerator cement solidification radioactive spent resin is characterized in that, described composite minerals additive is the mixture of zeolite, slag, silicon ash and flyash, and zeolite, slag, silicon ash are 5: 10: 9 with the mass ratio of flyash: 4.
3. according to the described a kind of use NaAlO of claim 1
2The method of setting accelerator cement solidification radioactive spent resin is characterized in that, 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.
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN105130305A (en) * | 2015-08-25 | 2015-12-09 | 武汉理工大学 | Alkaline slag cement solidification method for boron-containing waste resin of nuclear power plant |
WO2016045491A1 (en) * | 2014-09-24 | 2016-03-31 | 深圳航天科技创新研究院 | Chemically bonded cementitious material for solidification of radioactive waste resin and solidification method |
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 |
CN114420334A (en) * | 2021-12-20 | 2022-04-29 | 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 |
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JP2000284092A (en) * | 1999-01-29 | 2000-10-13 | Toshiba Corp | Method and device for treating waste containing boron |
CN101456715A (en) * | 2008-12-25 | 2009-06-17 | 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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JP2000284092A (en) * | 1999-01-29 | 2000-10-13 | Toshiba Corp | Method and device for treating waste containing boron |
CN101456715A (en) * | 2008-12-25 | 2009-06-17 | 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 |
Non-Patent Citations (2)
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Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2016045491A1 (en) * | 2014-09-24 | 2016-03-31 | 深圳航天科技创新研究院 | Chemically bonded cementitious material for solidification of radioactive waste resin and solidification method |
CN105130305A (en) * | 2015-08-25 | 2015-12-09 | 武汉理工大学 | Alkaline slag cement solidification method for boron-containing waste resin of nuclear power plant |
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 |
CN114420334A (en) * | 2021-12-20 | 2022-04-29 | 燕山大学 | Method for treating radioactive waste resin to obtain high-stability waste bag |
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 |
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