CN106960692B - Radioactive spent resin cement solidification formula and curing method - Google Patents
Radioactive spent resin cement solidification formula and curing method Download PDFInfo
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- CN106960692B CN106960692B CN201710145151.XA CN201710145151A CN106960692B CN 106960692 B CN106960692 B CN 106960692B CN 201710145151 A CN201710145151 A CN 201710145151A CN 106960692 B CN106960692 B CN 106960692B
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- water
- cement
- spent resin
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- 230000002285 radioactive effect Effects 0.000 title claims abstract description 60
- 238000007711 solidification Methods 0.000 title claims abstract description 40
- 230000008023 solidification Effects 0.000 title claims abstract description 40
- 239000003829 resin cement Substances 0.000 title claims abstract description 29
- 238000001723 curing Methods 0.000 title abstract description 7
- 239000011347 resin Substances 0.000 claims abstract description 83
- 229920005989 resin Polymers 0.000 claims abstract description 83
- 238000000034 method Methods 0.000 claims abstract description 29
- 229910021536 Zeolite Inorganic materials 0.000 claims abstract description 28
- HNPSIPDUKPIQMN-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Al]O[Al]=O HNPSIPDUKPIQMN-UHFFFAOYSA-N 0.000 claims abstract description 28
- 239000010457 zeolite Substances 0.000 claims abstract description 28
- 239000011398 Portland cement Substances 0.000 claims abstract description 27
- 239000003638 chemical reducing agent Substances 0.000 claims abstract description 27
- 235000008733 Citrus aurantifolia Nutrition 0.000 claims abstract description 24
- 235000011941 Tilia x europaea Nutrition 0.000 claims abstract description 24
- 239000004571 lime Substances 0.000 claims abstract description 24
- 238000003756 stirring Methods 0.000 claims abstract description 22
- 239000004568 cement Substances 0.000 claims description 43
- 239000000203 mixture Substances 0.000 claims description 36
- 239000002002 slurry Substances 0.000 claims description 35
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 32
- 230000018044 dehydration Effects 0.000 claims description 19
- 238000006297 dehydration reaction Methods 0.000 claims description 19
- 239000008367 deionised water Substances 0.000 claims description 10
- 229910021641 deionized water Inorganic materials 0.000 claims description 10
- 238000002156 mixing Methods 0.000 claims description 7
- 239000003795 chemical substances by application Substances 0.000 claims description 2
- 230000003467 diminishing effect Effects 0.000 claims description 2
- 239000000843 powder Substances 0.000 claims description 2
- 238000007667 floating Methods 0.000 abstract description 3
- 230000002940 repellent Effects 0.000 description 5
- 239000005871 repellent Substances 0.000 description 5
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 239000004575 stone Substances 0.000 description 4
- 238000003475 lamination Methods 0.000 description 2
- 238000012827 research and development Methods 0.000 description 2
- 229920002472 Starch Polymers 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000007664 blowing Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000000151 deposition Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 235000013399 edible fruits Nutrition 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- RMAQACBXLXPBSY-UHFFFAOYSA-N silicic acid Chemical compound O[Si](O)(O)O RMAQACBXLXPBSY-UHFFFAOYSA-N 0.000 description 1
- 235000012239 silicon dioxide Nutrition 0.000 description 1
- 235000019698 starch Nutrition 0.000 description 1
- 239000008107 starch Substances 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/307—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Curing Cements, Concrete, And Artificial Stone (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
The invention discloses a kind of radioactive spent resin cement solidification formulas and curing method suitable for stirring outside bucket for belonging to Radwastes treatment technical field.The formula uses ordinary portland cement, zeolite, lime, water-reducing agent, organosilicon and radioactive spent resin, the fluidity too small unloading difficulties that may cause being easy to appear in solidification process in effective solution radioactive spent resin bucket, the resin On The Floating that fluidity may cause greatly is overcome simultaneously, obtain that resin loading is big, solidified body meets the formula of requirements of the national standard.
Description
Technical field
The present invention relates to Radwastes treatment technical field more particularly to a kind of radioactive spent resin cement solidification formulas
And curing method.
Background technique
Nuclear power station and nuclear facilities operation and it is retired during can generate a large amount of radioactive spent resin, Spent Radioactive tree
The efficient process of rouge is one of the problem of long-standing problem China core career development.Cement solidification is that radioactive spent resin processing is universal
The method of use.
Current most of cement solidification production line all uses the method stirred in bucket, because stirring slurry itself can occupy
Certain volume, therefore can solidify above bucket the certain space of residue after the completion of stirring in bucket, usually bucket inner volume
15%~20%, cause the waste in space in bucket.
In order to which effectively using the volume for solidifying bucket, it is a kind of preferable selection that bucket stirs outside, but stirring technique outside bucket
The problem of depositing unloading difficulties after completion of stirring is easy to make simultaneously because the density ratio cement slurry of radioactive spent resin itself is light
There is lamination in cement slurry at radioactive spent resin and destroys uniformity.
Summary of the invention
The embodiment of the present invention provides a kind of radioactive spent resin cement solidification formula and curing method, suitable for stirring outside bucket
It mixes, it is possible to prevente effectively from stirring unloading difficulties outside bucket, and the floating of radioactive spent resin can be prevented.
A kind of radioactive spent resin cement solidification formula is suitable for stirring outside bucket comprising portland cement, zeolite, stone
Ash, water-reducing agent, organosilicon and radioactive spent resin, the mass ratio of various components is 1:0.01-0.05:0.01- in the formula
0.05:0.0005-0.005:0.001-0.02:0.4-0.6.
A kind of radioactive spent resin cement solidification method, comprising the following steps: by dehydration radioactive spent resin and organosilicon
It carries out mixed processing and obtains pretreatment resin；The silicic acid for being 1:0.01-0.05:0.01-0.05:0.0005-0.005 by mass ratio
Salt cement, zeolite, lime and water-reducing agent are uniformly mixed and obtain dry blend；By dry blend with pretreatment resin be mixed to get it is mixed
Object is closed, then water is added into mixture and is stirred to obtain cement slurry, wherein the mass ratio of dry blend, pretreatment resin and water is
1:0.3-1.0:0.1-0.3.
A kind of radioactive spent resin cement solidification method, comprising the following steps: obtain pretreatment resin step, dehydration is put
Penetrating property spent resin, which is added in organosilicon and deionized water, is pre-processed to obtain pretreatment resin, wherein dehydration Spent Radioactive tree
The mixing mass ratio of rouge, organosilicon and deionized water is 1:0.005-0.02:0.2-0.6；Dry blend step is obtained, by mass ratio
It is uniformly mixed for the portland cement of 1:0.01-0.05:0.01-0.05:0.0005-0.005, zeolite, lime and water-reducing agent
To dry blend；Cement slurry step is obtained, carries out dry blend and pretreatment resin to be mixed to get cement slurry.
Compared with prior art, radioactive spent resin cement solidification formula provided in an embodiment of the present invention and curing method
Using ordinary portland cement, zeolite, lime, water-reducing agent, organosilicon and radioactive spent resin, effective solution Spent Radioactive
The too small unloading difficulties that may cause of the fluidity being easy to appear in solidification process in resin barrel, while overcoming fluidity and greatly may be used
Resin On The Floating caused by energy, has obtained that resin loading is big, and solidified body meets the formula of requirements of the national standard.
Specific embodiment
The feature and exemplary embodiment of various aspects of the invention is described more fully below.In following detailed description
In, many details are proposed, in order to provide complete understanding of the present invention.But to those skilled in the art
It will be apparent that the present invention can be implemented in the case where not needing some details in these details.Below to implementation
The description of example is used for the purpose of providing by showing example of the invention and better understanding of the invention.
It should be noted that in the absence of conflict, the features in the embodiments and the embodiments of the present application can phase
Mutually combination.The application is described in detail below with reference to the accompanying drawings and in conjunction with the embodiments.
In order to which effectively using the volume for solidifying bucket, it is a kind of preferable selection that bucket stirs outside, but the Beater operator outside bucket
Special requirement is proposed in the use process of skill to cement solidification formula, that is, cement solidification formula must assure that cement slurry
There are enough mobility, just can guarantee that discharging after completion of stirring smoothly completes in this way, while the density ratio water of resin itself
Mud is light, and cement solidification formula must assure that cement slurry starts solidification faster and resin is avoided to occur lamination in cement slurry
And destroy uniformity.
Radioactive spent resin is carrying out the preceding all interim storages of cement solidification processing in a reservoir, and returning for the ease of resin
It takes and requires the resin that is soaked in water, in order to accurately measure resin, removed by mechanical rotary dehydration free on resin
Water weighs the weight of resin, available accurate dosage later.Therefore formula R&D process in using dehydration resin into
Row formula research and development.
Embodiment of the present invention provides a kind of radioactive spent resin cement solidification formula, is suitable for stirring outside bucket comprising
Portland cement, zeolite, lime, water-reducing agent, organosilicon and radioactive spent resin, the mass ratio of various components is 1 in the formula:
0.01-0.05:0.01-0.05:0.0005-0.005:0.001-0.02:0.4-0.6, preferably 1:0.02:0.03:
0.0015:0.005:0.5.Portland cement is common portland cement, and ordinary portland cement is marked as 42.5MPa.Boiling
Stone is ultrafine zeolite powder, and specific surface area is greater than 800m2/kg.Lime is that the content of Ca (OH) 2 is greater than 92% lime.Water-reducing agent
For non-air-entraining water-reducing agent, water-reducing agent can be UNF-5 type high efficiency water reducing agent.
Embodiment of the present invention also provides a kind of radioactive spent resin cement solidification method comprising following steps:
Dehydration radioactive spent resin and organosilicon mixed processing are obtained pretreatment resin by S10；
S20, portland cement, zeolite, the stone for being 1:0.01-0.05:0.01-0.05:0.0005-0.005 by mass ratio
Ash and water-reducing agent, which are uniformly mixed, obtains dry blend；
S30 carries out dry blend and pretreatment resin to be mixed to get mixture, then water is added into mixture and is stirred
Obtain cement slurry, wherein dry blend, pretreatment resin and water mass ratio be 1:0.3-1.0:0.1-0.3, preferably up to 1:
0.50:0.15；
S40 solidifies the cement slurry obtained by step S30, obtains radioactive spent resin cement solidification body.
In step S30, in cement slurry portland cement, zeolite, lime, water-reducing agent and organosilicon mass ratio be 1:
0.02:0.03:0.0015:0.005.
In step S10, organosilicon is added in dehydration radioactive spent resin and carries out being sufficiently mixed stirring.
Step S10 is first passed through to obtain pretreatment resin and then sequentially add lime, zeolite, portland cement and diminishing
Agent, wherein portland cement, zeolite, lime, water-reducing agent and organosilicon mass ratio be 1:0.01-0.05:0.01-0.05:
0.0005-0.005:0.001-0.02, preferably 1:0.02:0.03:0.0015:0.005.
Water can be deionized water in step S30.
Step S10, S20 and/or S30 can be stirred the stirring of mixture outside bucket.
Cement slurry obtained in step S30 is put into bucket in step s 40 or bucket solidifies outside.
Embodiment of the present invention also provides another radioactive spent resin cement solidification method comprising following steps:
Dehydration radioactive spent resin, organosilicon and deionized water mixed processing are obtained pretreatment resin, wherein institute by S100
The mixing mass ratio for stating dehydration radioactive spent resin, organosilicon and deionized water is 1:0.005-0.02:0.2-0.6；
S200, portland cement, zeolite, the stone for being 1:0.01-0.05:0.01-0.05:0.0005-0.005 by mass ratio
Ash and water-reducing agent, which are uniformly mixed, obtains dry blend；
S300 carries out dry blend and pretreatment resin to be mixed to get cement slurry；
S400 solidifies the cement slurry obtained by step S300, obtains radioactive spent resin cement solidification body.
In the step s 100, organosilicon and deionized water are added in dehydration radioactive spent resin and be sufficiently mixed stirring
It mixes.The mixing mass ratio for being wherein dehydrated radioactive spent resin, organosilicon and deionized water is 1:0.01:0.3.
In step s 200, the mass ratio of portland cement, zeolite, lime and water-reducing agent is 1:0.02:0.03:
0.0015。
Step S100, S200 and/or S300 can be stirred the stirring of mixture outside bucket.
Cement slurry obtained in step S300 is put into bucket in step S400 or is solidified outside bucket.
The radioactive spent resin cement solidification formula and curing method that embodiment of the present invention provides efficiently solve outside bucket
The problem of cement slurry blowing difficulty in whipping process, while the resin rising phenomenon being likely to occur is effectively prevented, solidified body is anti-
Compressive Strength meets national standard (> 7MPa) requirement, and solidified body surface is not cracked.
Radioactive spent resin cement solidification formula of the present invention and solidification is specifically described below by specific embodiment
Method.
Embodiment 1
It adds the powdered organosilicon moisture repellent of 1kg into 100kg dehydration resin and stirs evenly and stand 1 hour and obtain pre- place
Manage resin.
By ordinary portland cement, zeolite, lime and water-reducing agent with following mass ratio ratio 1:0.02:0.03:0.0015 into
Row is uniformly mixed and obtains dry blend.
Obtained dry blend made above is added in pretreatment resin, water is then added and is stirred to obtain cement
Slurry, wherein dry blend, pretreatment resin, water are mixed by following mass ratio 1:0.50:0.15.
Preparation-obtained cement slurry good fluidity, cement slurry are not layered, and resin is uniform in cement after solidification
Mixing, is not layered.The solidified body of radioactive spent resin cement solidification formula obtained by the above method meets country
The requirements of GB14569.1-2011.
Embodiment 2
100kg is dehydrated resin and the powdered organosilicon moisture repellent of 0.5kg stirs evenly and stands 1 hour and pre-processed
Resin.
Ordinary portland cement, zeolite, lime and water-reducing agent are mixed with following mass ratio 1:0.01:0.01:0.0005
Uniformly obtain dry blend.
Obtained dry blend made above is added in pretreatment resin, water is then added and is stirred, wherein dry-mixed
Material, pretreatment resin and water are carried out being mixed to get cement slurry by following mass ratio 1:0.3:0.3.
Preparation-obtained cement slurry good fluidity, cement slurry are not layered.According to cement obtained by the above method
Starch the requirements that preparation-obtained solidified body meets country GB14569.1-2011.
Embodiment 3
It adds the powdered organosilicon moisture repellent of 2kg into 100kg dehydration resin and stirs evenly and stand 1 hour and obtain pre- place
Manage resin.
Ordinary portland cement, zeolite, lime and water-reducing agent are mixed with following mass ratio 1:0.02:0.03:0.005
It is even to obtain dry blend.
Obtained dry blend made above is added in pretreatment resin, water is then added and is stirred, wherein dry-mixed
Material, pretreatment resin and water are carried out being mixed to get cement slurry by following mass ratio 1:1:0.15.
Preparation-obtained cement slurry good fluidity, is not layered.It is made according to cement slurry obtained by the above method
Standby obtained solidified body meets the requirements of country GB14569.1-2011.
Embodiment 4
100kg is dehydrated resin and the powdered organosilicon moisture repellent of 1kg stirs evenly and stands 1 hour and obtains pretreatment tree
Rouge.
Ordinary portland cement, zeolite, lime and water-reducing agent are mixed with following mass ratio 1:0.05:0.05:0.005
It is even to obtain dry blend.
Obtained dry blend made above is added in pretreatment resin, water is then added and is stirred, wherein dry-mixed
Material, pretreatment resin and water are carried out being mixed to get cement slurry by following mass ratio 1:0.8:0.15.
Preparation-obtained cement slurry good fluidity, is not layered.It is made according to cement slurry obtained by the above method
Standby obtained solidified body meets the requirements of country GB14569.1-2011.
Embodiment 5
100kg is dehydrated resin and the powdered organosilicon moisture repellent of 1kg stirs evenly and stands 1 hour and obtains pretreatment tree
Rouge.
Ordinary portland cement, zeolite, lime and water-reducing agent are mixed with following ratio 1:0.02:0.03:0.0010
It is even to obtain dry blend.
Obtained dry blend made above is added in pretreatment resin, water is then added and is stirred, wherein dry-mixed
Material, pretreatment resin and water are carried out being mixed to get cement slurry by following mass ratio 1:0.6:0.2.
Preparation-obtained cement slurry good fluidity, is not layered.It is made according to cement slurry obtained by the above method
Standby obtained solidified body meets the requirements of country GB14569.1-2011.
The present invention can realize in other specific forms, without departing from its spirit and essential characteristics.Therefore, current reality
Apply example be all counted as being exemplary rather than in all respects it is limited, the scope of the present invention by appended claims rather than on
Description definition is stated, also, falls into the meaning of claim and whole changes in the range of equivalent to all be included in this
Among the range of invention.Also, the different technologies feature occurred in different embodiments can be combined, to obtain beneficial to effect
Fruit.Those skilled in the art will be understood that and realize revealed on the basis of studying attached drawing, specification and claims
The embodiment of other variations of embodiment.
Claims (12)
1. a kind of radioactive spent resin cement solidification formula is suitable for stirring outside bucket characterized by comprising portland cement,
Zeolite, lime, water-reducing agent, organosilicon and radioactive spent resin, the mass ratio of various components is 1:0.01-0.05 in the formula:
0.01-0.05:0.0005-0.005:0.001-0.02:0.4-0.6.
2. radioactive spent resin cement solidification formula according to claim 1, which is characterized in that the radioactive spent resin
To be dehydrated radioactive spent resin, the portland cement, zeolite, lime, water-reducing agent, organosilicon and dehydration radioactive spent resin
Mass ratio is 1:0.02:0.03:0.0015:0.005:0.5.
3. radioactive spent resin cement solidification formula according to claim 1 or 2, which is characterized in that the zeolite is super
Thin zeolite powder, specific surface area are greater than 800m2/kg。
4. a kind of radioactive spent resin cement solidification method, comprising the following steps:
Dehydration radioactive spent resin and organosilicon mixed processing are obtained into pretreatment resin；
Portland cement, zeolite, lime and the diminishing for being 1:0.01-0.05:0.01-0.05:0.0005-0.005 by mass ratio
Agent is uniformly mixed and obtains dry blend；
It carries out the dry blend and the pretreatment resin to be mixed to get mixture, then water is added into the mixture and carries out
Cement slurry is stirred to get, wherein the mass ratio of the dry blend, pretreatment resin and water is 1:0.3-1.0:0.1-0.3.
5. radioactive spent resin cement solidification method according to claim 4, which is characterized in that the dehydration Spent Radioactive
The mixed proportion of resin and organosilicon is 1:0.005-0.02.
6. radioactive spent resin cement solidification method according to claim 5, which is characterized in that the dehydration Spent Radioactive
The mixed proportion of resin and organosilicon is 1:0.01.
7. radioactive spent resin cement solidification method according to claim 4, which is characterized in that first obtain the pretreatment
Resin and then sequentially add the lime, zeolite, portland cement and water-reducing agent, wherein the portland cement, zeolite,
The mass ratio of lime, water-reducing agent and organosilicon is 1:0.01-0.05:0.01-0.05:0.0005-0.005:0.001-0.02.
8. radioactive spent resin cement solidification method according to claim 7, which is characterized in that the portland cement,
Zeolite, lime, water-reducing agent and organosilicon mass ratio be 1:0.02:0.03:0.0015:0.005.
9. radioactive spent resin cement solidification method according to claim 4, which is characterized in that the dry blend, pre- place
The mass ratio for managing resin and water is 1:0.50:0.15.
10. a kind of radioactive spent resin cement solidification method, comprising the following steps:
Pretreatment resin step is obtained, dehydration radioactive spent resin, organosilicon and deionized water mixed processing are pre-processed
Resin, wherein the mixing mass ratio of the dehydration radioactive spent resin, organosilicon and deionized water is 1:0.005-0.02:0.2-
0.6；
Obtain dry blend step, by mass ratio be 1:0.01-0.05:0.01-0.05:0.0005-0.005 portland cement,
Zeolite, lime and water-reducing agent are uniformly mixed and obtain dry blend；
Cement slurry step is obtained, carries out the dry blend and the pretreatment resin to be mixed to get cement slurry.
11. radioactive spent resin cement solidification method according to claim 10, which is characterized in that described to be pre-processed
In resin step, the mixing mass ratio of the dehydration radioactive spent resin, organosilicon and deionized water is 1:0.01:0.3.
12. radioactive spent resin cement solidification method described in 0 or 11 according to claim 1, which is characterized in that described to be done
In mixing step, the portland cement, zeolite, lime and water-reducing agent mass ratio be 1:0.02:0.03:0.0015.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910022690.3A CN109903876B (en) | 2017-03-10 | 2017-03-10 | Radioactive waste resin cement curing slurry and preparation method thereof |
| CN201710145151.XA CN106960692B (en) | 2017-03-10 | 2017-03-10 | Radioactive spent resin cement solidification formula and curing method |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201710145151.XA CN106960692B (en) | 2017-03-10 | 2017-03-10 | Radioactive spent resin cement solidification formula and curing method |
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| CN201910022690.3A Division CN109903876B (en) | 2017-03-10 | 2017-03-10 | Radioactive waste resin cement curing slurry and preparation method thereof |
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| CN106960692B true CN106960692B (en) | 2019-02-26 |
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| CN115159917B (en) * | 2022-07-05 | 2023-05-26 | 中国核电工程有限公司 | Formula and method for curing and treating radioactive waste resin by cement |
Family Cites Families (19)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2717656A1 (en) * | 1977-04-21 | 1978-10-26 | Nukem Gmbh | PROCESS FOR THE PRODUCTION OF LEAK-RESISTANT AND SALINE-RESISTANT BLOCKS FROM CEMENT AND RADIOACTIVE WASTE |
| JP2513690B2 (en) * | 1987-05-22 | 1996-07-03 | 電気化学工業株式会社 | Solidifying agent for radioactive waste |
| JPH01223398A (en) * | 1988-03-03 | 1989-09-06 | Denki Kagaku Kogyo Kk | Radioactive waste hardener |
| JP2523891B2 (en) * | 1989-08-30 | 1996-08-14 | 株式会社日立製作所 | Method for solidifying radioactive waste |
| US6743963B2 (en) * | 1998-12-21 | 2004-06-01 | Perma-Fix Environmental Services, Inc. | Methods for the prevention of radon emissions |
| CN101456715B (en) * | 2008-12-25 | 2012-07-18 | 清华大学 | Boron-containing radioactive spent resin cement solidification method |
| CN102034560B (en) * | 2010-10-18 | 2013-02-27 | 清华大学 | Method for solidifying radioactive waste resin cement |
| CN102010161A (en) * | 2010-10-29 | 2011-04-13 | 清华大学 | Method for preventing resin from floating in cementation of radioactive spent resin |
| CN102176333A (en) * | 2011-02-28 | 2011-09-07 | 清华大学 | Method for increasing irradiation stability of cement solidified body for radioactive spent resin |
| CN102176334A (en) * | 2011-03-09 | 2011-09-07 | 清华大学 | Method for improving soaking resistance of solidification body in radioactive spent resin cement solidification |
| CN102262911B (en) * | 2011-05-19 | 2013-10-16 | 清华大学 | Method for solidifying waste radioactive resins with naphthalene series water reducer and cement |
| WO2013075322A1 (en) * | 2011-11-25 | 2013-05-30 | 中国广东核电集团有限公司 | Cement curing formulation and method for high-level radioactive boron waste resins from nuclear reactor |
| JP5190975B1 (en) * | 2012-03-27 | 2013-04-24 | 株式会社太平洋コンサルタント | Solidification method for combustible waste incineration ash and its solidified body |
| CN103886927A (en) * | 2012-12-21 | 2014-06-25 | 中核核电运行管理有限公司 | Radioactive waste resin curing formula |
| CN103886926A (en) * | 2012-12-21 | 2014-06-25 | 中核核电运行管理有限公司 | Radioactive concentrated liquor solidifying formula |
| JP6139288B2 (en) * | 2013-06-18 | 2017-05-31 | 株式会社東芝 | Method and apparatus for solidifying cement of waste liquid containing boric acid |
| CN105679390B (en) * | 2014-11-18 | 2018-07-13 | 中国辐射防护研究院 | Nuclear power station failure drier mixing volume reduction solidification processing method |
| 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 |
| CN105976886A (en) * | 2016-05-10 | 2016-09-28 | 中国核电工程有限公司 | Radioactive waste curing method |
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2017
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| Publication number | Publication date |
|---|---|
| CN109903876A (en) | 2019-06-18 |
| CN106960692A (en) | 2017-07-18 |
| CN109903876B (en) | 2020-07-31 |
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