CN102169737A - High-salt high-alkali Medium-low-level radioactive liquid waste cement solidified body and preparation method thereof - Google Patents
High-salt high-alkali Medium-low-level radioactive liquid waste cement solidified body and preparation method thereof Download PDFInfo
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Abstract
The invention discloses a high-salt high-alkali medium-low-level radioactive liquid waste cement solidified body which is composed by mixing the following components: high-salt high-alkali medium-low-level radioactive liquid waste and, solidification material, water glass and cellulose ether, wherein the high-salt high-alkali medium-low-level radioactive liquid waste to the solidification material is 0.55-0.75: 1 in mass proportion; the modulus of the water glass is 2.5-3.5 based on Na2O in the water glass and the mass of the solidification material is 1-3% of the mass of the water glass ; the mass of the solidification material is 0.05-0.5% of the mass of the cellulose ether; the component mass percent of the solidification material is as follows: 20-40% of low-heat Portland cement, 15-50% of slag powder, 15-30% of coal ash, 5-15% of zeolite and 5-15% of attapulgite; and the cement solidification body with various properties meeting the requirements is obtained by carrying out normal-temperature maintenance on the mixed slurry which obtained by mixing and stirring. The high-salt high-alkali medium-low-level radioactive liquid waste cement solidified body is suitable for the solidification of the medium-low-level radioactive liquid waste, which has the total salt concentration being 100-400g/L, the pH value being larger than 13 and the nuclide being 90Sr or/and 137 Cs.
Description
Technical field
The invention belongs to radioactive-waste disposal, solidify to handle, relate to a kind of high salt high-alkali in low-level radioactive liquid waste solidified cement body and preparation method thereof.Being specially adapted to total salt concentration is 100～400g/L, its pH value＞13, and contained leading ion is Na
+, AlO
2 -, NO
3 -, CO
3 2-, PO
4 3-, SO
4 2-, or/and OH
-And nucleic
90Sr or/and
137Among the Cs, the curing of low-level radioactive liquid waste handles.
Background technology
The radioactive waste that is produced by devices such as the aftertreatment of nuclear fuel, all kinds of nuclear reactor, nuclear power stations has suitable harmfulness, can not be directly to environmental emission, must be cured with suitable method and by the proper device compartmentalized storage, up to wherein radioelement decay to environment do not produced harm till.At present, in, the curing of low-level radioactive waste handles and mainly adopts cement solidification, and also obtained commercial Application.But in, the form of low-level radioactive waste is various, it is in close relations that its composition and state of aggregation and curing materials are selected, therefore, the prescription of firming body also will adapt with specific radioactive waste.
In, in the low-level radioactive waste, nucleic
90Sr,
137Cs is most important two kinds, and their productive rate is higher, the half life period long (
90The half life period of Sr is 27.7a,
137Cs is 30.5a), along with the prolongation of this class radioactive waste resting period, the proportion that their radioactivity accounts for the mixed fission product gross activity is bigger.Radioactive nuclide has specific radiobiology toxicity, wherein strontium, caesium belong to middle and high toxicity (as:
90Sr,
137Need such as Cs just can decay to harmless level through centuries even longer time), because of they exist with ionic species usually, in water, have very strong transfer ability.Therefore, in, the firming body of low-level radioactive waste must have stronger retentivity to these two kinds of nucleic.
The curing of low-level radioactive liquid waste had certain degree of difficulty during high salt was high-alkali, and reason has the following aspects: the existence of great amount of soluble salt makes the containing amount to waste liquid of firming body reduce; Soluble-salt can make prolong the setting time of mixture slurry; Salt is separated out from the firming body surface easily; The anti-immersion performance of firming body descends, and causes the leaching rate increase of firming body etc.
In the prior art, the curing materials of middle low-level radioactive waste mainly is a portland cement, is mixed with the portland-type cement of pozzolana mixed materials such as silicon ash, slag, flyash.Because the portland cement mineral composition, its hydration heat is bigger, makes temperature rising in the firming body, may cause micro-crack, influences the firming body permanance.There are some researches show that the hydrated product of portland cement is poor to the adsorptive power of nucleic ion, unfavorable to the curing of nucleic.Mix its permanance of portland-type cement with volcanic debris composite material (as slag, flyash etc.) and increase, hydration heat descends to some extent, but early strength is lower, its hydrated product to nucleic (as
90Sr,
137Cs) adsorptive power is still relatively poor, and the leaching rate of nucleic still is in higher level in the firming body.In the cement of portland cement and volcanic debris composite material formation, mix adsorbent again, as: zeolite etc., main in order to improve the adsorptive power of firming body to nucleic, thereby increase the retentivity of firming body to nucleic, the result of this technical measures can make the leaching rate of nucleic descend, but the intensity of firming body has certain decline.If with this class material directly solidify high salt high-alkali in, during the low-activity waste liquid, in fact constituted the curing materials system of alkali-pozzolana mixed material-portland cement-adsorbent, but portland cement mesosilicic acid DFP (is designated hereinafter simply as C at present
3S) content generally reaches 50%～60%, and the content of dicalcium silicate is generally 20%～25% and (is designated hereinafter simply as C
2S).As everyone knows, the early strength height of alkali-pozzolana mixed material, the C in the portland cement
3S also is early strong mineral, C
2S can make firming body later stage and long-term strength increase.The blended cement that alkali-pozzolana mixed material-portland cement constitutes, the material of performance early strength is too much, and the long-term mechanical property of firming body is difficult to guarantee, even produces the strength retraction phenomenon.As, the curing materials system proportioning of this alkali-pozzolana mixed material-portland cement-adsorbent is improper, if and the participation that does not have the agent of mixture slurry Properties Control, tend to occur deficiencies such as wayward, easy bleeding mixture slurry setting time, thereby cause firming body inhomogeneous, finally cause leaching rate higher.
Alkali slag cement be a kind of be the Binder Materials of primary raw material with alkali-activator and GBFS; it has mechanical property (especially early strength height) preferably, endurance quality and to the retention performance of nucleic, the research that is applied to the solidification of radwaste aspect is also more.Other there are some researches show, mixes metakaolin and adsorbent and can make hydrated product in the firming body to nucleic in alkali slag cement
90Sr,
137The Cs adsorptive power improves, firming body
90Sr,
137The Cs leaching rate reduces.But alkali slag cement does not still have national standard at present, and condenses too fastly because of it, and the composition of its mechanical property and slag and thermal history are very big, and strength fluctuation is big, and its application is restricted.Therefore, the curing materials of alkali slag cement class still is in conceptual phase at present.For solidify with it high salt high-alkali in, low-level radioactive liquid waste still do not have report.
In the prior art, at high salt high-alkali in, mainly there is following problem in the prescription of the firming body of low-level radioactive liquid waste:
(1) high salt high-alkali in low-level radioactive liquid waste be solidified with its singularity, if the firming body prescription is improper, the firming body long-term strength may occurs and be difficult to guarantee; In the solidification process, mixture slurry setting time deficiency such as wayward, easy bleeding, thereby cause firming body inhomogeneous, finally cause leaching rate higher;
(2) alkali slag cement class curing materials is detained nucleic
90Sr,
137The Cs ability is strong, but its mechanical property is big with fluctuation, and setting time is short, and no national standard is used limited.
Summary of the invention
Purpose of the present invention is intended to overcome above-mentioned deficiency of the prior art, provide a kind of high salt high-alkali in low-level radioactive liquid waste solidified cement body and preparation method thereof.The present invention with high salt high-alkali in, low-level radioactive liquid waste is as one of composition material, with low-heat portland cement, slag powders, flyash, zeolite, attapulgite (polygorskite) is a main raw material(s), water glass, cellulose ether is the Properties Control agent, pass through proportion design, adopt suitable liquid-solid ratio, through stirring, obtaining fluidity is the mixture slurry of 160～220mm, after the normal temperature maintenance, the various stable performances of the solidified cement body that obtains are good, meet the requirement of GB14569.1-1993 " low; middle horizontal radiation solidification of waste body performance requirement-solidified cement body ", thus be high salt high-alkali in, the cement solidification of low-level radioactive liquid waste is laid a good foundation.
Design of the present invention is:
(1) with high salt high-alkali in, the alkaline constituents in the low-level radioactive liquid waste is as the chemical activator of firming body composition material-slag powders, flyash, make the compositional system of curing materials become the hydrated blended cement system of alkali-slag-fly ash-low-heat portland cement-adsorbent, realize that alkali excites the combination of Binder Materials, low-heat portland cement and adsorbent.This combination, the hydration heat of integrated low-heat portland cement is low, long-term mechanical property stable, later strength is high and alkali excites epistasis energy morning, endurance quality, hydrated product and the adsorbent of the Binder Materials excellence high absorption property to nucleic, thereby improves firming body to nucleic ability to cure and long-time stability;
(2) modulus be 2.5～3.5, volume at 1～3% water glass (with Na
2O meter) both as alkali-activator, can be used as the set accelerator of mixture slurry again, with presetting period of guaranteeing mixture slurry greater than 2 hours, final setting time is no more than 15 hours; Cellulose ether mainly plays water retention, prevents that the excreting water phenomenon of mixture slurry from taking place, and separates out alkali to prevent the firming body surface, thereby guarantees the homogeneity of firming body;
(3) in the firming body, low-heat portland cement proportion in the solid phase powder body material is no more than 40%, but adopts slag powders, flyash to come instead of part cement; The combination of alkaline constituents in the radioactive liquid waste and slag, flyash is equivalent to alkali and excites Binder Materials, guaranteeing the early strength of firming body, and a large amount of C in the low-heat portland cement
2The existence of S can guarantee the later stage and the long-term strength of firming body, and simultaneously, the hydration heat that the hydrated cementitious of firming body is produced is lower, and the temperature that guarantees firming body centre in the actual engineering does not cause in the firming body and cracks;
(4) can to improve firming body right for adsorbent
90Sr,
137The adsorptive power of Cs.
Content of the present invention is: low-level radioactive liquid waste solidified cement body during a kind of high salt is high-alkali, it is characterized in that: by mass ratio be high salt high-alkali in low-level radioactive liquid waste: solidifying substance (hereinafter to be referred as liquid-solid ratio)=0.55～0.75: low-level radioactive liquid waste and solidifying substance during 1 high salt is high-alkali, modulus be 2.5～3.5, with the Na in the water glass
2The water glass of O meter, solidifying substance quality 1～3%, and the cellulose ether of solidifying substance quality 0.05～0.5% mixes composition;
The component of described solidifying substance and mass percent example comprise: low-heat portland cement 20～40%, slag powders 15～50%, flyash 15～30%, zeolite 5～15% and attapulgite (having another name called polygorskite or Palygorskite) 5～15%.
In the content of the present invention: described zeolite can be that the mordenite of mass percentage content＞70% of zeolite is or/and clinoptilolite.
In the content of the present invention: low-level radioactive liquid waste was that total salt concentration is 100～400g/L during described high salt was high-alkali, pH value＞13, and contained leading ion is Na
+, AlO
2 -, NO
3 -, CO
3 2-, PO
4 3-, SO
4 2-, or/and OH
-And nucleic
90Sr or/and
137Among the Cs, low-level radioactive liquid waste.
Another content of the present invention is: the preparation method of low-level radioactive liquid waste solidified cement body during a kind of high salt is high-alkali is characterized in that may further comprise the steps:
A, batching: in mass ratio be high salt high-alkali in low-level radioactive liquid waste: solidifying substance=0.55～0.75: 1 ratio get high salt high-alkali in low-level radioactive liquid waste and solidifying substance, the delivery number is 2.5～3.5, with the Na in the water glass
2The water glass of the solidifying substance quality 1～3% of O meter is got the cellulose ether of solidifying substance quality 0.05～0.5%;
The component of described solidifying substance and mass percent example comprise: low-heat portland cement 20～40%, slag powders 15～50%, flyash 15～30%, zeolite 5～15% and attapulgite (having another name called polygorskite or Palygorskite) 5～15%, get each component by described mass percent example;
B, preparation firming body: each component of the described solidifying substance of step a, water glass, cellulose ether are placed in (specific) container, again with described high salt high-alkali in low-level radioactive liquid waste join in the container, mixed 5～10 minutes, make uniform mixture slurry, again mixture slurry is placed in the solidification of radwaste bucket, under the normal temperature maintenance promptly make high salt high-alkali in the solidified cement body of low-level radioactive liquid waste.This solidified cement body is after maintenance, and the various performances of the solidified cement body that obtains meet the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
In another content of the present invention: the fluidity of mixture slurry described in the step b is preferably in 160～220mm scope.
In another content of the present invention: zeolite described in the step a is that the mordenite of mass percentage content＞70% of zeolite is or/and clinoptilolite.
In another content of the present invention: low-level radioactive liquid waste was that total salt concentration is 100～400g/L during high salt described in the step a was high-alkali, pH value＞13, and contained leading ion is Na
+, AlO
2 -, NO
3 -, CO
3 2-, PO
4 3-, SO
4 2-, or/and OH
-And nucleic
90Sr or/and
137Among the Cs, low-level radioactive liquid waste.
Compared with prior art, the present invention has following characteristics and beneficial effect:
(1) the present invention with high salt high-alkali in, low-level radioactive liquid waste is as alkali-activator, make it with composition material in slag powders, flyash generation hydration reaction, form hydrated product with gelling ability; These hydrated products are to nucleic
90Sr,
137The adsorptive power of Cs is stronger, thereby has increased the retentivity of firming body to nucleic; Both make full use of strong advantage morning that alkali excites Binder Materials, simultaneously, utilized low-heat portland cement later stage, advantage that long-term strength is high again, helped guaranteeing the stability of firming body;
On composition of the present invention and reaction principle, this is a compound cement system, has the gelling ability component two parts are arranged: a part is alkali-slag-fly ash cement, belongs to alkali and excites a kind of of Binder Materials; Another part is a low-heat portland cement.Alkali-slag-fly ash cement disintegrates vitreum by sillico aluminate glass body in alkaline constituents activated slag in the waste liquid and the flyash, generates the aquation silico-aluminate gel with gelling ability.The chemical composition of these aquation silico-aluminate gels is different with the hydrated product of portland cement, and its principal ingredient is Na
2O, CaO, Al
2O
3, SiO
2, H-
2O, and the main hydration products of portland cement is the hydrated calcium silicate gel of high calcium silicon ratio, principal ingredient is CaO, SiO
2, H-
2O, average calcium silicon ratio is about 1.75.We studies show that, aquation silico-aluminate gel has than the stronger adsorptive power of silicate cement hydration product simulation nucleic strontium, caesium, reason is that the aluminium in the aquation silico-aluminate gel has replaced silicon, sodium has replaced calcium, produce remaining negative charge, thereby the ability of aquation silico-aluminate gel absorption kation (as cesium ion) is strengthened.This point is even more important to the cesium ion that is difficult to solidify.Aspect mechanical property, this cement has early strong, fast hardware features, good endurance, but later strength enhancement rate is little.If this cement and portland cement is compound, then owing to C in the Portland clinker
3S content is 50%～60%, C
2The content of S is generally 20%～25%, as seen is with C
3S is great majority.Because C
3S early hydration speed is fast, and the early strength development is fast, and the enhancement rate of later strength compares C
2S is little, so the material of keeping the later strength growth in the hydrated blended cement system of alkali-slag-fly ash-portland cement is few, even the phenomenon of later stage or long-term strength retraction can occur;
The mineral composition of low-heat portland cement is different with portland cement.C in the low-heat portland cement
2The content of S reaches 45%～60%, and C
3S has only 20%～30%.Alkali-slag-fly ash cement and low-heat portland cement is compound, both made full use of strong advantage morning that alkali excites Binder Materials, simultaneously, utilize low-heat portland cement later stage, advantage that long-term strength is high again, help guaranteeing the stability of firming body;
(2) adopt the present invention, the application of slag powders, flyash, low-heat portland cement helps reducing the hydration heat amount of solidifying substance mesosilicic acid salt cement, thereby has reduced the central temperature of firming body, reduces the generation of micro-crack in the firming body;
(3) adopt the present invention, the use of water glass both can have been made the exciting agent of slag and flyash, can shorten setting time again.Water glass itself is alkaline matter, is the exciting agent of slag and flyash, and is similar with the effect of alkaline constituents.During high salt is high-alkali, pH value of low-level radioactive liquid waste, salt content, liquid-solid ratio etc. all can influence the performance of condensing of mixture slurry.According to our research work, salt increases, and prolong setting time; Liquid-solid ratio increases and prolongs setting time.For the flowability of solidifying physical efficiency containing radioactive waste as much as possible and guaranteeing mixture slurry, liquid-solid ratio will reach 0.55～0.75 usually.This mixture slurry presetting period will reach more than 8 hours usually, and final setting time is sometimes greater than 15 hours.And the prolongation of setting time can increase the bleeding of mixture slurry, causes firming body inhomogeneous up and down.It is set accelerator that the present invention adopts water glass, and along with the increase of water glass volume, shorten setting time, and the silicate ion in its principle water glass is an active ion, has very extensive chemical reaction capacity, it can with Na in the alkaline constituents
+, the Ca of the vitreum in slag and the flyash after disintegrating
2+, the Ca (OH) that produces of low-heat portland cement aquation
2React, generation has the hydrated product of gelling ability, thereby shortened setting time.Therefore, can by in high-alkali according to high salt, low-level radioactive liquid waste pH value, salt content, liquid-solid ratio mix water glass in right amount and regulate setting time;
(4) adopt the present invention, the use of cellulose ether can prevent that mixture slurry from producing excreting water phenomenon;
Firming body of the present invention has constituted a compound cement system, has taken into account the advantage that low-heat portland cement and alkali excite Binder Materials, and material is easy to get, and technology is simple; Its practical effect is mainly reflected in the following aspects: (a) use of low-heat portland cement makes the firming body mechanical property more stable; (b) leaching rate of firming body strontium, caesium is low than the portland cement firming body, the leaching rate requirement that is better than stipulating among the GB14569.1-1993, and under equal conditions, the leaching rate of strontium, caesium only is 1/5 of a portland cement firming body; (c) use of cellulose ether has effectively prevented from the bleeding of mixture slurry to make firming body more even; (d) setting time of mixture slurry can be effectively shortened in the use of water glass, and its volume what can pass through, and controls the length of setting time;
The present invention helps forming and meets the solidified cement body that GB14569.1-1993 requires, for high salt high-alkali in, the cement solidification engineering of low-level radioactive liquid waste haves laid a good foundation;
(5) preparation technology of the present invention is simple, need not to acquire specialized equipment, and operation is easy, and operation is practical easily.
Embodiment
Embodiment given below intends so that the invention will be further described; but can not be interpreted as it is limiting the scope of the invention; the person skilled in art to some nonessential improvement and adjustment that the present invention makes, still belongs to protection scope of the present invention according to the content of the invention described above.
Embodiment 1:
Low-level radioactive liquid waste solidified cement body and preparation method thereof during a kind of high salt is high-alkali comprises:
In 42.5 grade low-heat portland cements: slag powders: flyash: zeolite: (wt.% is the mass percent example to the ratio of attapulgite (polygorskite)=40wt.%: 20wt.%: 20wt.%: 10wt.%: 10wt.%, the back is together) the weighing material, be mixed and made into solidifying substance.With the solidifying substance is benchmark, and weighing 0.1% cellulose ether, 1.0%(are with wherein Na
2O meter) modulus is that 2.5～3.5 water glass places same container respectively.In salt content be 200g/L, pH value＞14 in, low-level radioactive liquid waste: the ratio of solidifying substance (hereinafter to be referred as liquid-solid ratio)=0.65 measures radioactive liquid waste; Get radioactive liquid waste and join in the above-mentioned container that fills solidifying substance, water glass, cellulose ether, stirred 10 minutes, make uniform mixture slurry; By liquid-solid ratio control mixture slurry fluidity is 175mm; The mixture slurry of preparation is placed in the solidification of radwaste bucket maintenance under the normal temperature; In the 6 hours 50 minutes presetting period of mixture slurry, final setting time is 10 hours 15 minutes.28 days compressive strength of firming body is 20.5MPa, and the leaching rate of 42 days Sr is 1.4 * 10
-4Cm.d
-1, Cs leaching rate be 2.4 * 10
-4Cm.d
-1, all the other performances all satisfy the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
Embodiment 2:
Low-level radioactive liquid waste solidified cement body and preparation method thereof during a kind of high salt is high-alkali comprises:
In 42.5 grade low-heat portland cements: slag powders: flyash: zeolite: attapulgite (polygorskite)=30wt.%: 40wt.%: 15wt.%: 10wt.%: 5wt.% ratio weighing material is mixed and made into solidifying substance.With the solidifying substance is benchmark, and weighing 2.5%(is with wherein Na
2O meter) modulus is that 2.5～3.5 water glass, 0.1% cellulose ether place same container respectively.In salt content be 300g/L, pH value＞14 in, low-level radioactive liquid waste: the ratio of solidifying substance (hereinafter to be referred as liquid-solid ratio)=0.65 measures radioactive liquid waste; Get radioactive liquid waste and join in the above-mentioned container that fills solidifying substance, water glass, cellulose ether, stirred 10 minutes, make uniform mixture slurry.By liquid-solid ratio control mixture slurry fluidity is 170mm; The mixture slurry of preparation is placed in the solidification of radwaste bucket maintenance under the normal temperature.In the 6 hours 15 minutes presetting period of mixture slurry, final setting time is 8 hours 50 minutes; 28 days compressive strength of firming body is 18.5MPa, and the leaching rate of 42 days Sr is 1.8 * 10
-4Cm.d
-1, Cs leaching rate be 2.7 * 10
-4Cm.d
-1, all the other performances all satisfy the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
Embodiment 3:
Low-level radioactive liquid waste solidified cement body and preparation method thereof during a kind of high salt is high-alkali comprises:
A, batching: in mass ratio be high salt high-alkali in low-level radioactive liquid waste: the ratio of solidifying substance=0.75: 1 get high salt high-alkali in low-level radioactive liquid waste and solidifying substance, the delivery number is 2.5～3.5, with the Na in the water glass
2The water glass of the solidifying substance quality 3% of O meter is got the cellulose ether of solidifying substance quality 0.5%;
The component of described solidifying substance and mass percent example comprise: low-heat portland cement 40%, slag powders 15%, flyash 30%, zeolite 5% and attapulgite 10%, get each component by described mass percent example;
B, preparation firming body: each component of the described solidifying substance of step a, water glass, cellulose ether are placed in (specific) container, again with described high salt high-alkali in low-level radioactive liquid waste join in the container, mixed 10 minutes, make uniform mixture slurry, again mixture slurry is placed in the solidification of radwaste bucket, under the normal temperature maintenance promptly make high salt high-alkali in the solidified cement body of low-level radioactive liquid waste; This solidified cement body is after maintenance, and the various performances of the solidified cement body that obtains promptly meet the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
Embodiment 4:
Low-level radioactive liquid waste solidified cement body and preparation method thereof during a kind of high salt is high-alkali comprises:
A, batching: in mass ratio be high salt high-alkali in low-level radioactive liquid waste: the ratio of solidifying substance=0.55: 1 get high salt high-alkali in low-level radioactive liquid waste and solidifying substance, the delivery number is 2.5～3.5, with the Na in the water glass
2The water glass of the solidifying substance quality 1% of O meter is got the cellulose ether of solidifying substance quality 0.05%;
The component of described solidifying substance and mass percent example comprise: low-heat portland cement 20%, slag powders 50%, flyash 20%, zeolite 5% and attapulgite 5%, get each component by described mass percent example;
B, preparation firming body: each component of the described solidifying substance of step a, water glass, cellulose ether are placed in (specific) container, again with described high salt high-alkali in low-level radioactive liquid waste join in the container, mixed 5 minutes, make uniform mixture slurry, again mixture slurry is placed in the solidification of radwaste bucket, under the normal temperature maintenance promptly make high salt high-alkali in the solidified cement body of low-level radioactive liquid waste; This solidified cement body is after maintenance, and the various performances of the solidified cement body that obtains promptly meet the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
Embodiment 5:
Low-level radioactive liquid waste solidified cement body and preparation method thereof during a kind of high salt is high-alkali comprises:
A, batching: in mass ratio be high salt high-alkali in low-level radioactive liquid waste: the ratio of solidifying substance=0.65: 1 get high salt high-alkali in low-level radioactive liquid waste and solidifying substance, the delivery number is 2.5～3.5, with the Na in the water glass
2The water glass of the solidifying substance quality 2% of O meter is got the cellulose ether of solidifying substance quality 0.2%;
The component of described solidifying substance and mass percent example comprise: low-heat portland cement 30%, slag powders 30%, flyash 20%, zeolite 10% and attapulgite 10%, get each component by described mass percent example;
B, preparation firming body: each component of the described solidifying substance of step a, water glass, cellulose ether are placed in (specific) container, again with described high salt high-alkali in low-level radioactive liquid waste join in the container, mixed 8 minutes, make uniform mixture slurry, again mixture slurry is placed in the solidification of radwaste bucket, under the normal temperature maintenance promptly make high salt high-alkali in the solidified cement body of low-level radioactive liquid waste; This solidified cement body is after maintenance, and the various performances of the solidified cement body that obtains promptly meet the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
Embodiment 6-12:
Low-level radioactive liquid waste solidified cement body and preparation method thereof during a kind of high salt is high-alkali comprises:
A, batching: in mass ratio be high salt high-alkali in low-level radioactive liquid waste: solidifying substance=0.55～0.75: 1 ratio get high salt high-alkali in low-level radioactive liquid waste and solidifying substance, the delivery number is 2.5～3.5, with the Na in the water glass
2The water glass of the solidifying substance quality 1～3% of O meter is got the cellulose ether of solidifying substance quality 0.05～0.5%; (described scope in any point mass ratio all can);
The component of described solidifying substance and mass percent example comprise: low-heat portland cement 20～40%, slag powders 15～50%, flyash 15～30%, zeolite 5～15% and attapulgite (having another name called polygorskite or Palygorskite) 5～15%, get each component by described mass percent example; Among each embodiment in the solidifying substance the concrete mass percent example of each component see the following form:
B, preparation firming body: each component of the described solidifying substance of step a, water glass, cellulose ether are placed in (specific) container, again with described high salt high-alkali in low-level radioactive liquid waste join in the container, mixed 5～10 minutes, make uniform mixture slurry, again mixture slurry is placed in the solidification of radwaste bucket, under the normal temperature maintenance promptly make high salt high-alkali in the solidified cement body of low-level radioactive liquid waste; This solidified cement body is after maintenance, and the various performances of the solidified cement body that obtains promptly meet the requirement of GB14569.1-1993 " low, middle horizontal radiation solidification of waste body performance requirement-solidified cement body ".
In the foregoing description 3-12: the fluidity of mixture slurry described in the step b is preferably in 160～220mm scope.
In the foregoing description 3-12: zeolite described in the step a can be that the mordenite of mass percentage content＞70% of zeolite is or/and clinoptilolite (promptly adopting zeolite group mineral); Described low-heat portland cement can be that 42.5 grade low-heat portland cements, described slag powders can be 95 grade slag powders, and described flyash can be the first level flour coal ash.
In the foregoing description 3-12: low-level radioactive liquid waste was that total salt concentration is 100～400g/L during high salt described in the step a was high-alkali, pH value＞13, and contained leading ion is Na
+, AlO
2 -, NO
3 -, CO
3 2-, PO
4 3-, SO
4 2-, or/and OH
-And nucleic
90Sr or/and
137Among the Cs, low-level radioactive liquid waste.
In the foregoing description: the technological parameter of each step and numerical value etc. are scope, and any point is all applicable.
The not concrete same prior art of narrating of technology contents in content of the present invention and the foregoing description.
The invention is not restricted to the foregoing description, content of the present invention is described all can implement and have described good result.
Claims (7)
- A high salt high-alkali in low-level radioactive liquid waste solidified cement body, it is characterized in that: by mass ratio be high salt high-alkali in low-level radioactive liquid waste: solidifying substance=0.55～0.75: low-level radioactive liquid waste and solidifying substance during 1 high salt is high-alkali, modulus be 2.5～3.5, with the Na in the water glass 2The water glass of O meter, solidifying substance quality 1～3%, and the cellulose ether of solidifying substance quality 0.05～0.5% mixes composition;The component of described solidifying substance and mass percent example comprise: low-heat portland cement 20～40%, slag powders 15～50%, flyash 15～30%, zeolite 5～15% and attapulgite 5～15%.
- By the described high salt of claim 1 high-alkali in low-level radioactive liquid waste solidified cement body, it is characterized in that: described zeolite is that the mordenite of mass percentage content＞70% of zeolite is or/and clinoptilolite.
- By claim 1 or 2 described high salt high-alkali in low-level radioactive liquid waste solidified cement body, it is characterized in that: low-level radioactive liquid waste was that total salt concentration is 100～400g/L during described high salt was high-alkali, pH value＞13, contained leading ion is Na +, AlO 2 -, NO 3 -, CO 3 2-, PO 4 3-, SO 4 2-, or/and OH -And nucleic 90Sr or/and 137Among the Cs, low-level radioactive liquid waste.
- A high salt high-alkali in the preparation method of low-level radioactive liquid waste solidified cement body, it is characterized in that may further comprise the steps:Batching: in mass ratio be high salt high-alkali in low-level radioactive liquid waste: solidifying substance=0.55～0.75: 1 ratio get high salt high-alkali in low-level radioactive liquid waste and solidifying substance, the delivery number is 2.5～3.5, with the Na in the water glass 2The water glass of the solidifying substance quality 1～3% of O meter is got the cellulose ether of solidifying substance quality 0.05～0.5%;The component of described solidifying substance and mass percent example comprise: low-heat portland cement 20～40%, slag powders 15～50%, flyash 15～30%, zeolite 5～15% and attapulgite 5～15%, get each component by described mass percent example;Preparation firming body: each component of the described solidifying substance of step a, water glass, cellulose ether are placed in the container, again with described high salt high-alkali in low-level radioactive liquid waste join in the container, mixed 5～10 minutes, make uniform mixture slurry, again mixture slurry is placed in the solidification of radwaste bucket, under the normal temperature maintenance promptly make high salt high-alkali in the solidified cement body of low-level radioactive liquid waste.
- By the described high salt of claim 4 high-alkali in the preparation method of low-level radioactive liquid waste solidified cement body, it is characterized in that: the fluidity of mixture slurry described in the step b is in 160～220mm scope.
- By claim 4 or 5 described high salt high-alkali in the preparation method of low-level radioactive liquid waste solidified cement body, it is characterized in that: zeolite described in the step a is that the mordenite of mass percentage content＞70% of zeolite is or/and clinoptilolite.
- By claim 4 or 5 described high salt high-alkali in the preparation method of low-level radioactive liquid waste solidified cement body, it is characterized in that: low-level radioactive liquid waste was that total salt concentration is 100～400g/L during high salt described in the step a was high-alkali, pH value＞13, contained leading ion are Na +, AlO 2 -, NO 3 -, CO 3 2-, PO 4 3-, SO 4 2-, or/and OH -And nucleic 90Sr or/and 137Among the Cs, low-level radioactive liquid waste.
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| CN103680660A (en) * | 2013-12-03 | 2014-03-26 | 南京大学 | Application of cullet in solidifying radionuclide and normal temperature solidifying method for waste comprising radioactive Cs+ |
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| CN103680660A (en) * | 2013-12-03 | 2014-03-26 | 南京大学 | Application of cullet in solidifying radionuclide and normal temperature solidifying method for waste comprising radioactive Cs+ |
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| CN104299668A (en) * | 2014-09-24 | 2015-01-21 | 深圳航天科技创新研究院 | Geological cement for solidification of radioactive incineration ash and solidification method of radioactive incineration ash |
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| CN111799009A (en) * | 2020-07-31 | 2020-10-20 | 中核四川环保工程有限责任公司 | Method for solidifying radioactive waste scintillation liquid |
| CN111799009B (en) * | 2020-07-31 | 2024-04-19 | 中核四川环保工程有限责任公司 | Method for solidifying radioactive waste scintillation liquid |
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