CN1092110A - Concentrate the method for separating actinide elements the high activity liquid waste from producing heap - Google Patents
Concentrate the method for separating actinide elements the high activity liquid waste from producing heap Download PDFInfo
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- CN1092110A CN1092110A CN93102120A CN93102120A CN1092110A CN 1092110 A CN1092110 A CN 1092110A CN 93102120 A CN93102120 A CN 93102120A CN 93102120 A CN93102120 A CN 93102120A CN 1092110 A CN1092110 A CN 1092110A
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- extraction
- actinide elements
- waste liquid
- high activity
- waste
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- 229910052768 actinide Inorganic materials 0.000 title claims abstract description 19
- 150000001255 actinides Chemical class 0.000 title claims abstract description 19
- 238000000034 method Methods 0.000 title claims abstract description 19
- 239000010808 liquid waste Substances 0.000 title claims abstract description 17
- 230000000694 effects Effects 0.000 title abstract description 14
- 239000012141 concentrate Substances 0.000 title abstract description 7
- 238000000605 extraction Methods 0.000 claims abstract description 59
- XYFCBTPGUUZFHI-UHFFFAOYSA-N Phosphine Chemical compound P XYFCBTPGUUZFHI-UHFFFAOYSA-N 0.000 claims abstract description 20
- 239000007788 liquid Substances 0.000 claims abstract description 20
- 239000012074 organic phase Substances 0.000 claims abstract description 19
- 239000002699 waste material Substances 0.000 claims abstract description 18
- 238000005406 washing Methods 0.000 claims abstract description 13
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 claims abstract description 12
- 229910000073 phosphorus hydride Inorganic materials 0.000 claims abstract description 10
- 239000003350 kerosene Substances 0.000 claims abstract description 7
- 102100040653 Tryptophan 2,3-dioxygenase Human genes 0.000 claims abstract 2
- 101710136122 Tryptophan 2,3-dioxygenase Proteins 0.000 claims abstract 2
- 229910052695 Americium Inorganic materials 0.000 claims description 16
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 claims description 16
- 229910052778 Plutonium Inorganic materials 0.000 claims description 12
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 12
- 229910052781 Neptunium Inorganic materials 0.000 claims description 11
- 229910052770 Uranium Inorganic materials 0.000 claims description 11
- LFNLGNPSGWYGGD-UHFFFAOYSA-N neptunium atom Chemical compound [Np] LFNLGNPSGWYGGD-UHFFFAOYSA-N 0.000 claims description 11
- 229910052761 rare earth metal Inorganic materials 0.000 claims description 11
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 11
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 claims description 9
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 claims description 6
- 230000002285 radioactive effect Effects 0.000 claims description 4
- 235000006408 oxalic acid Nutrition 0.000 claims description 3
- 150000002910 rare earth metals Chemical class 0.000 claims description 3
- 229910000029 sodium carbonate Inorganic materials 0.000 claims description 3
- 239000002253 acid Substances 0.000 claims description 2
- 230000008929 regeneration Effects 0.000 claims description 2
- 238000011069 regeneration method Methods 0.000 claims description 2
- 238000010025 steaming Methods 0.000 claims description 2
- 239000000758 substrate Substances 0.000 claims description 2
- 239000012071 phase Substances 0.000 claims 2
- 239000007864 aqueous solution Substances 0.000 abstract description 15
- 230000008901 benefit Effects 0.000 abstract description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 4
- 230000007613 environmental effect Effects 0.000 abstract description 3
- 238000012545 processing Methods 0.000 abstract description 3
- 230000005855 radiation Effects 0.000 abstract description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 2
- 239000003795 chemical substances by application Substances 0.000 description 9
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 6
- 239000000243 solution Substances 0.000 description 6
- 230000004992 fission Effects 0.000 description 5
- 239000000203 mixture Substances 0.000 description 5
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 4
- 229910017604 nitric acid Inorganic materials 0.000 description 4
- 150000001875 compounds Chemical class 0.000 description 3
- 229910052742 iron Inorganic materials 0.000 description 3
- 239000004215 Carbon black (E152) Substances 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 2
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 229910052767 actinium Inorganic materials 0.000 description 2
- QQINRWTZWGJFDB-UHFFFAOYSA-N actinium atom Chemical compound [Ac] QQINRWTZWGJFDB-UHFFFAOYSA-N 0.000 description 2
- KBPLFHHGFOOTCA-UHFFFAOYSA-N caprylic alcohol Natural products CCCCCCCCO KBPLFHHGFOOTCA-UHFFFAOYSA-N 0.000 description 2
- 239000003085 diluting agent Substances 0.000 description 2
- 239000000284 extract Substances 0.000 description 2
- 229930195733 hydrocarbon Natural products 0.000 description 2
- 150000002430 hydrocarbons Chemical class 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 235000017550 sodium carbonate Nutrition 0.000 description 2
- BWDBEAQIHAEVLV-UHFFFAOYSA-N 6-methylheptan-1-ol Chemical compound CC(C)CCCCCO BWDBEAQIHAEVLV-UHFFFAOYSA-N 0.000 description 1
- 229910052685 Curium Inorganic materials 0.000 description 1
- OAICVXFJPJFONN-UHFFFAOYSA-N Phosphorus Chemical compound [P] OAICVXFJPJFONN-UHFFFAOYSA-N 0.000 description 1
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 1
- 150000001257 actinium Chemical class 0.000 description 1
- 125000000217 alkyl group Chemical group 0.000 description 1
- 239000004411 aluminium Substances 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- 229910052792 caesium Inorganic materials 0.000 description 1
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 125000004432 carbon atom Chemical group C* 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 230000002939 deleterious effect Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 238000003113 dilution method Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 230000003278 mimic effect Effects 0.000 description 1
- TVMXDCGIABBOFY-UHFFFAOYSA-N n-Octanol Natural products CCCCCCCC TVMXDCGIABBOFY-UHFFFAOYSA-N 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 229910052698 phosphorus Inorganic materials 0.000 description 1
- 239000011574 phosphorus Substances 0.000 description 1
- 239000000700 radioactive tracer Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 235000019600 saltiness Nutrition 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000011780 sodium chloride Substances 0.000 description 1
- 239000002904 solvent Substances 0.000 description 1
- 229910052712 strontium Inorganic materials 0.000 description 1
- CIOAGBVUUVVLOB-UHFFFAOYSA-N strontium atom Chemical compound [Sr] CIOAGBVUUVVLOB-UHFFFAOYSA-N 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Images
Classifications
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
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- Extraction Or Liquid Replacement (AREA)
Abstract
The present invention concentrates the method for separating actinide elements the high radiation waste liquid from producing heap, belongs to the technology of the processing of the high activity liquid waste that the aftertreatment of reactor spent fuel produces.This technology selects for use tributyl phosphate (TBP)-trialkyl phosphine (TRPO)-kerosene extraction system that the actinide elements that concentrates in the high radioactivity waste liquid is carried out multi-stage counter current extraction, washing, make actinide elements enter organic phase, water becomes the aqueous solution that does not contain αHe Su.Technology of the present invention is reasonable, greatly reduces the processing costs of high activity liquid waste.Have huge economy and environmental benefit.
Description
The invention belongs to the treatment process of the high radioactivity waste liquid of reactor spent fuel aftertreatment generation,
The research that separates the actinium element from high activity liquid waste is the advanced subject of nuclear energy safe utilization and field of environment protection; during fuel fission; except generating fission product; because uranium nuclear capture neutron generates nucleic such as neptunium, plutonium, americium, curium and enters high activity liquid waste; short-life fission product is deposited behind the 300-500 harmless to the mankind, deposits 10 and contain the radioactive transuranium element of long-life alpha
6In year or deleterious, must isolate with biosphere.If can separate economically the actinide elements in the high activity liquid waste is fairly simple, send that transmuting becomes short-life fission product in the reactor back to, security of nuclear fuel round-robin and economy all can improve, and this plays an important role to the development that promotes nuclear undertaking.
Chinese patent CN85105352.1 is illustrated the method for separating actinide elements from radioactive liquid waste, but this patent can only be handled the low saline salinity radioactive liquid waste.It is big that China produces heap high activity liquid waste cycles of concentration, is 20-50 times of common high activity liquid waste, adopts CN85105352.1 patent extraction of actinides will produce second organic phase, and continuous countercurrent extraction can't be carried out.
In order to eliminate the generation of second organic phase, can adopt following way: first kind: with spissated high activity liquid waste dilution, its salt concentration is reduced, use trialkyl phosphine in the CN85105352.1 patent (TRPO) extraction system to carry out counter-current extraction again, can eliminate second organic phase like this, but will dilute 3-5 at least doubly, the secondary waste liquid amount is greatly increased, extraction agent is corresponding with the reverse-extraction agent consumption also will to be increased, and from environmental angle, this scheme is unreasonable.Second method: add other solvent such as n-Octanol, isooctyl alcohol waits until in the trialkyl phosphine extraction system, like this, during actinide elements in the extraction high activity liquid waste, second organic phase can not occur.But in this technical process, the distribution ratio of americium is very little, influences the extraction yield of americium.
At above-mentioned contradiction, the object of the present invention is to provide a kind of compound extracting system is tributyl phosphate (TBP)-trialkyl phosphine (TRPO)-kerosene extraction system, the actinide elements that concentrates in the high radioactivity waste liquid is carried out the separation processes method, this method is not only avoided occurring second organic phase in the extraction process, and has guaranteed the extraction yield of americium and other actinium element.
It is tributyl phosphate (TBP)-trialkyl phosphine (TRPO)-kerosene that main points of the present invention are to select for use the compound extracting system does not have element and carries out multi-stage counter current extraction, washing concentrating actinium series in the high waste liquid, actinide elements americium in the waste liquid, rare earth, neptunium, plutonium, uranium extraction are arrived organic phase, load organic phases is stripped with salpeter solution, oxalic acid solution, sodium carbonate solution successively, and the organic phase after the back extraction recycles after regeneration.
It is the 200-400 grams per liter that the present invention handles the residual substrate concentration of the total steaming of high activity liquid waste
Wherein contain about 0.6 mol-0.9 of aluminium mol
Iron is the 0.2-0.4 mol
Sodium is the 0.2-0.3 mol
Nickel is the 0.1-0.2 mol
Strontium, caesium, uranium are that trace, neptunium, plutonium, americium are tracer level.
Stream ratio in the extraction process: organic phase/water is 1/3-3/1; 20 ℃-30 ℃ of extraction temperature; Tributyl phosphate concentration is the 15-25%(percent by volume in the extraction system), trialkyl phosphorus concentration is the 25-35%(percent by volume); Extraction section extraction progression is the 11-15 level, and washing progression is the 4-8 level.Extraction equipment can be selected mixer-settler, centrifugal extractor or column extractor for use.The molecular formula of trialkyl phosphine is R
3PO, wherein R is the alkyl of 6-8 carbon atom, be liquid at normal temperatures, can close hydrocarbon diluent (for example kerosene) and dissolve each other with full, tributyl phosphate then is an extraction agent commonly used in the coring industry, have very high irradiation stability, can close hydrocarbon diluent and dissolve each other with full again, tributyl phosphate-trialkyl phosphine-kerosene system be a uniform organic solution like this.Tributyl phosphate extracts for example iron etc. of a part of major element, has alleviated the extraction load of trialkyl phosphine and has improved ability to the actinide elements extraction, and can eliminate the generation of second organic phase again.The present invention has selected rational extraction sum of series washing progression, thereby concentrating the high radioactivity waste liquid makes actinide elements and rare earth element enter organic phase through extraction, the aqueous solution that contains fission product and major constituents iron, sodium etc. becomes and does not contain alpha-active solution, and organic phase is multiplexing again after back extraction.
The present invention has the following advantages: (1) has eliminated second organic phase that occurs in extraction process, has guaranteed that actinide elements extraction process process realizes extraction system smoothly in the high activity liquid waste to concentrating.(2) avoided dilution method to produce a large amount of secondary waste liquids and a large amount of extraction agents of use and strippant.(3) the easy purifying of the extraction system of selecting for use, low price has good radiation-resistant property.
Describe the present invention below in conjunction with accompanying drawing
Fig. 1 is a process flow sheet of the present invention
Concentrated high activity liquid waste (F) is from 1 section latter half of adding and carry out counter-current extraction from the extraction system (0) of the 1st grade of adding, actinide elementss such as the americium of required extraction all enter organic phase, also extracted simultaneously the nucleic that part need not be extracted, therefore, need add washing composition (S from 1 section final stage
1), the part that flush away need not extract, the aqueous solution (W) after extraction is discharged from 1 section first step.
The organic extraction system that contains actinide elements enters 2 sections, for reextraction americium and rare earth element from extraction agent, from 2 sections latter half of adding strippant (S
2), contain the aqueous solution (P of americium and rare earth
1) collect from 2 sections first step.Add washing composition (S from 2 sections final stages
3), contained part acid in the flush away extraction system (0) is for next step reextraction plutonium and neptunium are prepared.The extraction system of load (0) enters 3 sections and strippant (S again
4) counter current contact, resultingly contain plutonium, the neptunium aqueous solution of back extraction is P
2The load extraction liquid that so only contains uranium element enters 4 sections, again with anti-stripping agent (S
5) counter current contact, obtain uraniferous aqueous solution of back extraction (P
3), exhausted extraction system (O) is used through reprocessing cycle.
Description of drawings
Fig. 1 is a process flow sheet of the present invention
1 extraction section among the figure
2 americiums and rare earth element reextraction section
The reextraction section of 3 neptuniums and plutonium
The reextraction section of 4 uranium
F concentrates the high radioactivity waste liquid
S
1Washing composition
O compound extracting system
The W raffinate
S
2Americium and rare earth element reverse-extraction agent
S
3Americium and rare earth element stripping section washing composition
P
1Contain the americium and the rare earth element aqueous solution
S
4Neptunium and plutonium stripping section reverse-extraction agent
P
2Contain neptunium, the plutonium aqueous solution
S
5The stripping section reverse-extraction agent of uranium
P
3Uranium containing water solution
O
1Need regenerated extraction system to go out
Embodiment: under 25 ℃ of temperature, carry out tandem test (seeing Fig. 1 flow process), process described in describing by flow process, concrete data are as follows:
F: the simulated high-level radioactive waste that contains 0.4-0.8 mol nitric acid
O: its composition of extraction system is the trialkyl phosphine-kerosene of (15-25%) tributyl phosphate-(25-35%)
S
1: the washings that contains 0.7-1.0 mol nitric acid
S
2: contain the reextraction americium of 4.0-5.5 mol nitric acid, the aqueous solution of rare earth element
S
3: the washings that contains 0.1-0.3 mol nitric acid
S
4: contain the reextraction neptunium of 0.3-0.7 mol oxalic acid, the aqueous solution of plutonium
S
5: the aqueous solution that contains 5%-12% yellow soda ash reextraction uranium
Progression: 1 section 16-20 level
2 sections 8-12 levels
3 sections 6-8 levels
4 sections 6-8 levels
Add up to: the 36-48 level
The stream ratio: organic phase/water is 1/3-3/1
Obtain three kinds of aqueous solution P respectively
1, P
2, P
3
P
1: contain 99.9% the americium and the aqueous solution of rare earth element
P
2: contain 99.9% the neptunium and the aqueous solution of plutonium
P
3: the aqueous solution that contains 99.5% uranium
Concentrate actinide elementss such as the americium that successfully extracted the high radiation waste liquid greater than 99.9%, neptunium, plutonium, uranium from mimic, proof the present invention has practical value, extend in the processing of the high high radioactivity waste liquid of saltiness, the high radioactivity waste liquid that contains αHe Su of large volume is resolved into the waste liquid that contains αHe Su of small volume and the non-α waste liquid of large volume, greatly reduce the expense of further disposal, this will have great economic benefit and environmental benefit.
Claims (4)
1, a kind of extraction system of trialkyl phosphine that comprises is separated the method for actinide elements from acid radioactive liquid waste, it is characterized in that the extracted organic phase system of selecting for use is tributyl phosphate (TBP)-trialkyl phosphine (TRPO)-kerosene, extraction system and concentrated high radioactivity waste liquid carry out multi-stage counter current extraction, washing, in the organic extractant phase system, load organic phases is used salpeter solution successively with the actinide elements americium in the waste liquid, rare earth, neptunium, plutonium, uranium extraction; Oxalic acid solution, sodium carbonate solution is stripped, and the organic extractant phase system after the back extraction recycles after regeneration.
2, in accordance with the method for claim 1, the residual substrate concentration of steaming that it is characterized in that described concentrated high radioactivity waste liquid is the 200-400 grams per liter.
3,, it is characterized in that tributyl phosphate concentration is the 15-25%(percent by volume in the described extracted organic phase system according to the described method of claim 1.2), the concentration of trialkyl phosphine is the 25-35%(percent by volume).
4, according to the described method of claim 1.2.3, it is characterized in that described multi-stage counter current extraction, washing, extraction progression is the 11-15 level, and washing progression is the 4-8 level.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN93102120A CN1037914C (en) | 1993-03-04 | 1993-03-04 | Method for separating actinide elements from concentrated high-radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN93102120A CN1037914C (en) | 1993-03-04 | 1993-03-04 | Method for separating actinide elements from concentrated high-radioactive waste liquid |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1092110A true CN1092110A (en) | 1994-09-14 |
| CN1037914C CN1037914C (en) | 1998-04-01 |
Family
ID=4983961
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN93102120A Expired - Fee Related CN1037914C (en) | 1993-03-04 | 1993-03-04 | Method for separating actinide elements from concentrated high-radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN1037914C (en) |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN100424016C (en) * | 2006-08-18 | 2008-10-08 | 中国科学院长春应用化学研究所 | Method for preparing cerium trifluoride using neutral phosphoras (phosphine) extraction system |
| CN101561404B (en) * | 2009-06-05 | 2011-03-16 | 中国原子能科学研究院 | Method for determining plutonium age in trace plutonium sample |
| CN101561418B (en) * | 2009-06-05 | 2012-07-04 | 中国原子能科学研究院 | Method for determining plutonium age in trace plutonium sample |
| CN101561417B (en) * | 2009-06-05 | 2012-07-04 | 中国原子能科学研究院 | Method for determining plutonium age in trace plutonium sample |
| CN101593566B (en) * | 2008-05-30 | 2012-08-29 | 株式会社东芝 | Spent fuel reprocessing method |
| CN103305702A (en) * | 2013-07-08 | 2013-09-18 | 中国原子能科学研究院 | Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow |
| CN108152112A (en) * | 2017-12-18 | 2018-06-12 | 中核四0四有限公司 | Pu in a kind of low-activity sample,241Am and90The method of Sr separation determinations |
| CN112071461A (en) * | 2020-09-03 | 2020-12-11 | 清华大学 | Treatment method of high-fuel-consumption high-radioactivity waste liquid |
| CN112458283A (en) * | 2020-11-26 | 2021-03-09 | 浙江大学 | Phenanthroline phosphorus oxide and method for extracting and separating trivalent lanthanide and/or actinide ions |
| CN112941317A (en) * | 2019-12-10 | 2021-06-11 | 中核北方核燃料元件有限公司 | Uranium-containing waste liquid purification method |
| CN113082764A (en) * | 2021-04-27 | 2021-07-09 | 清华大学 | Extracting agent for radiation elements in phosphogypsum and using method thereof |
| CN115331862A (en) * | 2022-08-02 | 2022-11-11 | 清华大学 | Method for reducing concentration of zirconium ions in high-level radioactive waste liquid and treatment method of high-level radioactive waste liquid |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN85105352B (en) * | 1985-07-13 | 1988-12-07 | 清华大学 | Method for Separating Actinides from Radioactive Waste Liquid |
| CN1032596C (en) * | 1992-12-24 | 1996-08-21 | 清华大学 | Method for multi-stage fractionation and extraction of americium and rare-earth elements without complexing agent |
-
1993
- 1993-03-04 CN CN93102120A patent/CN1037914C/en not_active Expired - Fee Related
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN100424016C (en) * | 2006-08-18 | 2008-10-08 | 中国科学院长春应用化学研究所 | Method for preparing cerium trifluoride using neutral phosphoras (phosphine) extraction system |
| CN101593566B (en) * | 2008-05-30 | 2012-08-29 | 株式会社东芝 | Spent fuel reprocessing method |
| CN101561404B (en) * | 2009-06-05 | 2011-03-16 | 中国原子能科学研究院 | Method for determining plutonium age in trace plutonium sample |
| CN101561418B (en) * | 2009-06-05 | 2012-07-04 | 中国原子能科学研究院 | Method for determining plutonium age in trace plutonium sample |
| CN101561417B (en) * | 2009-06-05 | 2012-07-04 | 中国原子能科学研究院 | Method for determining plutonium age in trace plutonium sample |
| CN103305702B (en) * | 2013-07-08 | 2014-12-24 | 中国原子能科学研究院 | Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow |
| CN103305702A (en) * | 2013-07-08 | 2013-09-18 | 中国原子能科学研究院 | Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow |
| CN108152112A (en) * | 2017-12-18 | 2018-06-12 | 中核四0四有限公司 | Pu in a kind of low-activity sample,241Am and90The method of Sr separation determinations |
| CN112941317A (en) * | 2019-12-10 | 2021-06-11 | 中核北方核燃料元件有限公司 | Uranium-containing waste liquid purification method |
| CN112071461A (en) * | 2020-09-03 | 2020-12-11 | 清华大学 | Treatment method of high-fuel-consumption high-radioactivity waste liquid |
| CN112458283A (en) * | 2020-11-26 | 2021-03-09 | 浙江大学 | Phenanthroline phosphorus oxide and method for extracting and separating trivalent lanthanide and/or actinide ions |
| CN113082764A (en) * | 2021-04-27 | 2021-07-09 | 清华大学 | Extracting agent for radiation elements in phosphogypsum and using method thereof |
| CN115331862A (en) * | 2022-08-02 | 2022-11-11 | 清华大学 | Method for reducing concentration of zirconium ions in high-level radioactive waste liquid and treatment method of high-level radioactive waste liquid |
Also Published As
| Publication number | Publication date |
|---|---|
| CN1037914C (en) | 1998-04-01 |
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