CN104529281A - High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula - Google Patents
High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula Download PDFInfo
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- CN104529281A CN104529281A CN201410765615.3A CN201410765615A CN104529281A CN 104529281 A CN104529281 A CN 104529281A CN 201410765615 A CN201410765615 A CN 201410765615A CN 104529281 A CN104529281 A CN 104529281A
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- 239000004568 cement Substances 0.000 title claims abstract description 54
- 238000007711 solidification Methods 0.000 title claims abstract description 37
- 230000008023 solidification Effects 0.000 title claims abstract description 37
- 239000003513 alkali Substances 0.000 title claims abstract description 19
- 239000002925 low-level radioactive waste Substances 0.000 title abstract description 12
- 239000002926 intermediate level radioactive waste Substances 0.000 title abstract 6
- 239000007788 liquid Substances 0.000 claims abstract description 50
- 150000003839 salts Chemical class 0.000 claims abstract description 16
- 229960000892 attapulgite Drugs 0.000 claims abstract description 15
- 229910052625 palygorskite Inorganic materials 0.000 claims abstract description 15
- 239000002901 radioactive waste Substances 0.000 claims description 29
- 239000000203 mixture Substances 0.000 claims description 13
- 239000010881 fly ash Substances 0.000 claims description 11
- 239000011398 Portland cement Substances 0.000 claims description 4
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 claims description 2
- 239000011499 joint compound Substances 0.000 claims description 2
- 239000005368 silicate glass Substances 0.000 claims description 2
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 abstract description 8
- 238000011160 research Methods 0.000 abstract description 5
- 235000010344 sodium nitrate Nutrition 0.000 abstract description 4
- 239000004317 sodium nitrate Substances 0.000 abstract description 4
- 239000002002 slurry Substances 0.000 abstract description 3
- 239000002956 ash Substances 0.000 abstract description 2
- 239000010883 coal ash Substances 0.000 abstract 1
- 229910052500 inorganic mineral Inorganic materials 0.000 abstract 1
- 239000011707 mineral Substances 0.000 abstract 1
- 239000000843 powder Substances 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- 230000009466 transformation Effects 0.000 abstract 1
- 239000010808 liquid waste Substances 0.000 description 8
- 238000007906 compression Methods 0.000 description 6
- 230000006835 compression Effects 0.000 description 6
- 239000004615 ingredient Substances 0.000 description 6
- 238000012423 maintenance Methods 0.000 description 6
- 239000000463 material Substances 0.000 description 6
- 239000004570 mortar (masonry) Substances 0.000 description 6
- 230000002285 radioactive effect Effects 0.000 description 6
- 238000012360 testing method Methods 0.000 description 6
- 239000002699 waste material Substances 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 239000000654 additive Substances 0.000 description 5
- 230000000996 additive effect Effects 0.000 description 5
- 230000008014 freezing Effects 0.000 description 5
- 238000007710 freezing Methods 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 238000002156 mixing Methods 0.000 description 5
- 230000008569 process Effects 0.000 description 5
- 230000035939 shock Effects 0.000 description 5
- 238000002791 soaking Methods 0.000 description 5
- 238000010257 thawing Methods 0.000 description 5
- 230000008859 change Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 238000002386 leaching Methods 0.000 description 3
- 238000002360 preparation method Methods 0.000 description 3
- 238000010025 steaming Methods 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 2
- 230000015271 coagulation Effects 0.000 description 2
- 238000005345 coagulation Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000004088 simulation Methods 0.000 description 2
- 229940001516 sodium nitrate Drugs 0.000 description 2
- 239000000758 substrate Substances 0.000 description 2
- 238000010998 test method Methods 0.000 description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 229910021536 Zeolite Inorganic materials 0.000 description 1
- 239000002585 base Substances 0.000 description 1
- 238000011021 bench scale process Methods 0.000 description 1
- -1 breeze Inorganic materials 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- HNPSIPDUKPIQMN-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Al]O[Al]=O HNPSIPDUKPIQMN-UHFFFAOYSA-N 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000009472 formulation Methods 0.000 description 1
- 238000005469 granulation Methods 0.000 description 1
- 230000003179 granulation Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000009382 near-surface disposal Methods 0.000 description 1
- 239000004033 plastic Substances 0.000 description 1
- 229920003023 plastic Polymers 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 230000000284 resting effect Effects 0.000 description 1
- 235000019600 saltiness Nutrition 0.000 description 1
- 238000005185 salting out Methods 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
- 238000004017 vitrification Methods 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
- 239000003643 water by type Substances 0.000 description 1
- 239000010457 zeolite Substances 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
- Treatment Of Sludge (AREA)
Abstract
The invention discloses high-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula which is used for low and intermediate level waste solution with salt content of 200g/l to 300g/l and 80 percent of sodium nitrate. The low and intermediate level radioactive waste solution with 80 percent of sodium nitrate contains the following components: 0 to 5 percent by volume of slurry, 50 to 100 percent by mass of cement, 0 to 22.5 percent by mass of coal ash, 0 to 22.5 percent by mass of mineral powder and 0 to 5 percent by mass of attapulgite, wherein the ratio of liquid to ash is 0.55 to 0.65. The high-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula is already proved in the commissioning and continuous operation of a cement solidification engineering solidification line, and the performance of solid prepared by utilizing the formula not only can meet the national standard requirement, but also can promote the deployment of the solidification of high-salt high-alkali low and intermediate level radioactive waste solution (containing alpha slurry) and can accelerate the transformation of basic application scientific research to the engineering application.
Description
Technical field
The invention belongs to radioactive liquid waste solidification treatment field, be specifically related to the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt.
Background technology
Domestic and international for middle low radioactive waste liquid curing mode at present, adopt the treatment process that cement solidification, bituminization, plastics solidification, vitrification, prosthetic graft solidification, modified version cement solidification, ceramic solidification, granulation solidification etc. are different more.Cement solidification is the common technology of low radioactive waste liquid in process, has the advantages such as cured body stable performance, technological operation be simple, with low cost, is widely used in middle low radioactive waste liquid, steams the solidification treatment of raffinate, mud, spent resin, burning ash etc.Cement solidification principle is using cement as main inorganic gel curing substrate, also can mix flyash, attapulgite, breeze, zeolite etc. and change solidified cement body performance and the additive to nucleic absorption property, after these materials are mixed with refuse in proportion, add a certain amount of water or feed liquid again, the mortar formed, through maintenance after a while, forms solidified cement body.
The intermediate level liquid waste that spent fuel reprocessing plant produces comprise a large amount of sodium metaaluminate waste liquids that the molten shell of aftertreatment hot uranium element produces, in put the steaming raffinate of processing wastewater, desorb decontamination liquid; Low level waste water evaporated liquor is that low level waste water evaporation produces, a large amount of low level waste waters produced during low level waste water comprises nuclear installation production period, maintenance operation and in relevant retired activity; In put α mud be go back at the bottom of intermediate level liquid waste tank residue composition.In middle low radioactive waste liquid radioactivity β nucleic with
90sr,
137cs etc. are main, α-radionuclide
239+240pu,
241am etc. are main.Curing formula of the present invention in low-level waste source item very special and complicated, simultaneously dispose management expectancy according to national centering low-level waste, the many index of solidified cement body must meet the relevant criterion requirement of near surface disposal.
The technology of current high salt, high-alkali middle low radioactive waste liquid cement solidification formula, resting on curing mechanism research domestic more, the screening of laboratory scale curing additive, the Study on curing work of laboratory scale analog material liquid and laboratory scale dope the research of non-alpha slurry curing.For curing formula carry out true radioactive liquid waste solidification and carried out project scale checking and run continuously less, because curing formula exists certain otherness at simulated waste and true radioactive liquid waste solidification process, there is larger difference in bench scale pilot and project scale test.The high-alkali middle low radioactive waste liquid of high salt is when solidifying, and exist containing a large amount of salinities in waste liquid, cured body surface easily salting-out phenomenon occurs.
Now there is following problem for the high-alkali middle low radioactive waste liquid of high salt (containing α mud) cement solidification formula in the art: the research of (1) curing formula is carried out for simulated emission waste liquid more, utilize simulation nucleic to study, the formula carrying out true radioactive liquid waste solidification is less; (2) rest on the cold and hot checking work of laboratory scale more, carry out the less of engineer applied; (3) be applied to thermal test and project scale, for the cement solidification formula that low radioactive waste liquid, intermediate level liquid waste, α mud solidify simultaneously, there is no report at present.
Summary of the invention
The object of the invention is to solve problems of the prior art, provide one to be specially adapted to salinity in 200 ~ 300g/L, pH=11 ~ 13.5, main chemical compositions based on SODIUMNITRATE, radionuclide
90sr,
137cs,
60co, ∑ U,
239+240the low of Pu puts the high-alkali middle low radioactive waste liquid cement solidification formula of the high salt steaming raffinate and intermediate level liquid waste.
To achieve these goals, technical scheme of the present invention is, the high-alkali middle low radioactive waste liquid cement solidification formula of high salt, being applied to saltiness is the middle low radioactive waste liquid that 200 ~ 300g/l, wherein SODIUMNITRATE account for 80%, and it consists of: mud volume percent is 0 ~ 5%; Except mud, cement, flyash, breeze, attapulgite Four composition account for mass percent and are respectively 50 ~ 100%, 0 ~ 22.5%, 0 ~ 22.5% and 0 ~ 5%; Liquid gray scale is 0.55 ~ 0.65.
Described cement is ordinary Portland cement model is P.O42.5R, specific surface area ≮ 300m
2/ kg, granularity requirements is 80 μm of surplus sieves≤10%; Flyash density is 2.37g/cm
3, Blain specific surface ≮ 300m
2/ kg, granularity requirements is 80 μm of surplus sieves≤12%; Breeze is mainly containing alumina silicate glass body, and breeze density is 2.83g/cm
3, Blain specific surface: ≮ 350m
2/ kg; Attapulgite: content>=60%, density 2.12g/cm
3, Blain specific surface: ≮ 250m
2/ kg.
Preferred ingredient is: cement accounts for 100%, and liquid gray scale is 0.55.
Preferred ingredient is: cement, breeze, attapulgite account for mass percent and be respectively 50%, 45% and 5%, and liquid gray scale is 0.55.
Preferred ingredient is: mud volume percent is 5%; All the other components are cement, and liquid gray scale is 0.60.
Preferred ingredient is: mud volume percent is 5%; Cement, breeze, attapulgite account for mass percent and are respectively 50%, 45% and 5%, and liquid gray scale is 0.60.
Preferred ingredient is: mud volume percent is 10%; Cement, flyash, breeze, attapulgite account for mass percent and are respectively 50%, 22.5%, 22.5% and 5%, and liquid gray scale is 0.55.
The application is verified in the debugging of applicant's cement solidification engineering solidification line and continuous operation, the cured body performance prepared with this patent formula, not only meets the requirement of GB " GB14569.1-2011 ", " GB/T7023-2011 " and " GBT 1346-2011 "; And carrying out of high salt high-alkali middle low radioactive waste liquid (containing α mud) cement solidification can be promoted, the scientific research of quickening base application type is to the transition of engineer applied.
Embodiment
Below in conjunction with embodiment, the present invention is described further.
Preparation example
The present embodiment is using ordinary Portland cement P.O42.5R as main inorganic gel curing substrate, also can mix flyash, attapulgite, breeze etc. and change cement to the additive of nucleic absorption property, after these materials are mixed with refuse in proportion, the mortar formed, through maintenance after a while, forms solidified cement body.Concrete proportioning sees the following form:
Cold testing order: by true waste liquid and α mud, analog material liquid and the simulation mud of preparation 200g/L, 250g/L, 300g/L add in agitator kettle, cement and additive (flyash, breeze, attapulgite) Homogeneous phase mixing are added in agitator kettle by table 1 proportioning, mix and blend 10min.
Thermal test order: get true waste liquid and in put α mud first table 1 proportioning mixing after, join in agitator kettle, cement and additive (flyash, breeze, attapulgite) Homogeneous phase mixing added in agitator kettle by table 1 proportioning, mix and blend 10min.
Recommended formula 1
#degree of mobilization 218mm, presetting period 6:50, final setting time 9:10, ultimate compression strength 30.90MPa, shock resistance, anti-improving soaking, freezing and thawing performance etc. all meet the demands; Be recommended in low putting when steaming the process of production fluid to use.
Recommended formula 2
#degree of mobilization 215mm, presetting period 7:07, final setting time 8:17, ultimate compression strength 27.50MPa, shock resistance, anti-improving soaking, freezing and thawing performance etc. all meet the demands; Be recommended in process not have to use during the middle low radioactive waste liquid of α mud.
Recommended formula 3
#degree of mobilization 213mm, presetting period 7:09, final setting time 9:07, ultimate compression strength 31.53MPa, shock resistance, anti-improving soaking, freezing and thawing performance etc. all meet the demands; Recommended formula 4
#degree of mobilization 209mm, presetting period 7:44, final setting time 8:44, ultimate compression strength 27.84MPa, shock resistance, anti-improving soaking, freezing and thawing performance etc. all meet the demands; Recommended formula 5
#degree of mobilization 193mm, presetting period 10:43, final setting time 12:01, ultimate compression strength 16.04MPa, shock resistance, anti-improving soaking, freezing and thawing performance etc. all meet the demands.Rear three kinds of preferred ingredients containing mud component, for the treatment of containing low radioactive waste liquid in α mud; Wherein fill a prescription 3
#low radioactive waste liquid in lower for radioactive level, formula 4
#, 5
#be applied to the middle low radioactive waste liquid that radioactive level is higher; Formula 5
#add flyash component, its nucleic leaching effect is more excellent, but cost raises to some extent.
Above-mentioned cured body and mortar performance meet the requirement of GB " GB14569.1-2011 low, middle level radioactive waste cured body performance requriements solidified cement body ", " GB/T 7023-2011 low, middle level radioactive waste cured body standard leaching test method " and " GBT 1346-2011 cement normal consistency water consumption, time of coagulation, stability ".
Test example (400L engineering verification)
Press the formulation ratio of table 1 in the preparation of cement solidification line conditioner, the analog material liquid of 250g/L and volume ratio 5% simulate mud, and constant volume is to 8m
3, ordinary Portland cement P.O42.5R pours in cement bin.Now by pressing the liquid gray scale of 0.55, first 250g/L analog material liquid (containing mud) being poured in mixing agitator, then the cement pressure sky measured is poured in mixing agitator.After mix and blend 10min, mortar is poured in 400L regular barrel, and send the maintenance of maintenance station, maintenance is sampling and testing after 28 days.
Mortar flows degree at 180 ~ 220mm, presetting period 6 ~ 7h, final set 8 ~ 9h, ultimate compression strength > 7MPa.Cured body and mortar performance meet the requirement of GB " GB14569.1-2011 low, middle level radioactive waste cured body performance requriements solidified cement body ", " GB/T 7023-2011 low, middle level radioactive waste cured body standard leaching test method " and " GBT 1346-2011 cement normal consistency water consumption, time of coagulation, stability ".
Above embodiments of the invention are explained in detail, above-mentioned embodiment is only optimum embodiment of the present invention, but the present invention is not limited to above-described embodiment, in the ken that those of ordinary skill in the art possess, various change can also be made under the prerequisite not departing from present inventive concept.
Claims (7)
1. the high-alkali middle low radioactive waste liquid cement solidification formula of high salt, is characterized in that mud volume percent is 0 ~ 5%; Except mud, cement, flyash, breeze, attapulgite Four composition account for mass percent and are respectively 50 ~ 100%, 0 ~ 22.5%, 0 ~ 22.5% and 0 ~ 5%; Liquid gray scale is 0.55 ~ 0.65.
2. the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt as claimed in claim 1, is characterized in that cement be ordinary Portland cement model is P.O42.5R, specific surface area ≮ 300m
2/ kg, granularity requirements is 80 μm of surplus sieves≤10%; Flyash density is 2.37g/cm
3, Blain specific surface ≮ 300m
2/ kg, granularity requirements is 80 μm of surplus sieves≤12%; Breeze is mainly containing alumina silicate glass body, and breeze density is 2.83g/cm
3, Blain specific surface: ≮ 350m
2/ kg; Attapulgite: content>=60%, density 2.12g/cm
3, Blain specific surface: ≮ 250m
2/ kg.
3. the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt as claimed in claim 2, it is characterized in that cement accounts for 100%, liquid gray scale is 0.55.
4. the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt as claimed in claim 2, it is characterized in that cement, breeze, attapulgite account for mass percent and be respectively 50%, 45% and 5%, liquid gray scale is 0.55.
5. the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt as claimed in claim 2, it is characterized in that mud volume percent is 5%, all the other components are cement, and liquid gray scale is 0.60.
6. the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt as claimed in claim 2, is characterized in that mud volume percent is 5%; Cement, breeze, attapulgite account for mass percent and are respectively 50%, 45% and 5%, and liquid gray scale is 0.60.
7. the high-alkali middle low radioactive waste liquid cement solidification formula of a kind of high salt as claimed in claim 2, is characterized in that mud volume percent is 10%; Cement, flyash, breeze, attapulgite account for mass percent and are respectively 50%, 22.5%, 22.5% and 5%, and liquid gray scale is 0.55.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410765615.3A CN104529281A (en) | 2014-12-12 | 2014-12-12 | High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula |
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| CN201410765615.3A CN104529281A (en) | 2014-12-12 | 2014-12-12 | High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula |
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|---|---|
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| CN201410765615.3A Pending CN104529281A (en) | 2014-12-12 | 2014-12-12 | High-salt high-alkali low and intermediate level radioactive waste solution cement solidification formula |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106198171A (en) * | 2016-06-21 | 2016-12-07 | 中国科学院生态环境研究中心 | A kind of sample pretreating method of LIBS detection waste water and waste liquid |
| CN111268976A (en) * | 2020-03-23 | 2020-06-12 | 中核四川环保工程有限责任公司 | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof |
| CN114719268A (en) * | 2022-03-15 | 2022-07-08 | 中核四川环保工程有限责任公司 | A method for solidifying low-emission organic waste liquid and incinerating pyrolysis ash |
| CN115159920A (en) * | 2022-07-05 | 2022-10-11 | 中国核电工程有限公司 | Formula and method for solidifying cement by radioactive waste liquid |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102169737A (en) * | 2010-12-28 | 2011-08-31 | 西南科技大学 | High-salt high-alkali Medium-low-level radioactive liquid waste cement solidified body and preparation method thereof |
-
2014
- 2014-12-12 CN CN201410765615.3A patent/CN104529281A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102169737A (en) * | 2010-12-28 | 2011-08-31 | 西南科技大学 | High-salt high-alkali Medium-low-level radioactive liquid waste cement solidified body and preparation method thereof |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106198171A (en) * | 2016-06-21 | 2016-12-07 | 中国科学院生态环境研究中心 | A kind of sample pretreating method of LIBS detection waste water and waste liquid |
| CN111268976A (en) * | 2020-03-23 | 2020-06-12 | 中核四川环保工程有限责任公司 | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof |
| CN111268976B (en) * | 2020-03-23 | 2022-03-08 | 中核四川环保工程有限责任公司 | High-fluidity high-compactness cement curing material with middle-level radioactive waste liquid and curing method thereof |
| CN114719268A (en) * | 2022-03-15 | 2022-07-08 | 中核四川环保工程有限责任公司 | A method for solidifying low-emission organic waste liquid and incinerating pyrolysis ash |
| CN115159920A (en) * | 2022-07-05 | 2022-10-11 | 中国核电工程有限公司 | Formula and method for solidifying cement by radioactive waste liquid |
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Application publication date: 20150422 |