CN101994132B - Molten salt system based on oxide spent fuel dry-process aftertreatment - Google Patents
Molten salt system based on oxide spent fuel dry-process aftertreatment Download PDFInfo
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- CN101994132B CN101994132B CN201010555928A CN201010555928A CN101994132B CN 101994132 B CN101994132 B CN 101994132B CN 201010555928 A CN201010555928 A CN 201010555928A CN 201010555928 A CN201010555928 A CN 201010555928A CN 101994132 B CN101994132 B CN 101994132B
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- 150000003839 salts Chemical class 0.000 title claims abstract description 58
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims description 13
- 238000001035 drying Methods 0.000 title 1
- 238000000034 method Methods 0.000 claims abstract description 21
- -1 sodium aluminum fluoride Chemical compound 0.000 claims description 13
- 150000001875 compounds Chemical class 0.000 claims description 11
- 229910016569 AlF 3 Inorganic materials 0.000 claims description 9
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 claims description 9
- 229910052744 lithium Inorganic materials 0.000 claims description 9
- 230000008569 process Effects 0.000 claims description 7
- 238000002844 melting Methods 0.000 abstract description 4
- 230000008018 melting Effects 0.000 abstract description 4
- 229910044991 metal oxide Inorganic materials 0.000 abstract description 2
- KLZUFWVZNOTSEM-UHFFFAOYSA-K Aluminum fluoride Inorganic materials F[Al](F)F KLZUFWVZNOTSEM-UHFFFAOYSA-K 0.000 abstract 3
- 239000006172 buffering agent Substances 0.000 abstract 1
- 238000005260 corrosion Methods 0.000 abstract 1
- 230000007797 corrosion Effects 0.000 abstract 1
- 229910052808 lithium carbonate Inorganic materials 0.000 abstract 1
- 150000004706 metal oxides Chemical class 0.000 abstract 1
- PQXKHYXIUOZZFA-UHFFFAOYSA-M lithium fluoride Chemical compound [Li+].[F-] PQXKHYXIUOZZFA-UHFFFAOYSA-M 0.000 description 38
- 238000005516 engineering process Methods 0.000 description 7
- AIYUHDOJVYHVIT-UHFFFAOYSA-M caesium chloride Chemical compound [Cl-].[Cs+] AIYUHDOJVYHVIT-UHFFFAOYSA-M 0.000 description 6
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 5
- 239000010439 graphite Substances 0.000 description 5
- 238000012986 modification Methods 0.000 description 5
- 230000004048 modification Effects 0.000 description 5
- 238000005303 weighing Methods 0.000 description 5
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 4
- 229910052778 Plutonium Inorganic materials 0.000 description 4
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 4
- 239000003814 drug Substances 0.000 description 4
- 229940079593 drug Drugs 0.000 description 4
- 238000002474 experimental method Methods 0.000 description 4
- 230000004927 fusion Effects 0.000 description 4
- KWGKDLIKAYFUFQ-UHFFFAOYSA-M lithium chloride Chemical compound [Li+].[Cl-] KWGKDLIKAYFUFQ-UHFFFAOYSA-M 0.000 description 4
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 4
- 238000012805 post-processing Methods 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- 239000010935 stainless steel Substances 0.000 description 4
- 229910002804 graphite Inorganic materials 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 239000000155 melt Substances 0.000 description 3
- 239000000203 mixture Substances 0.000 description 3
- WJWSFWHDKPKKES-UHFFFAOYSA-N plutonium uranium Chemical compound [U].[Pu] WJWSFWHDKPKKES-UHFFFAOYSA-N 0.000 description 3
- 239000000843 powder Substances 0.000 description 3
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 description 2
- YCKRFDGAMUMZLT-UHFFFAOYSA-N Fluorine atom Chemical compound [F] YCKRFDGAMUMZLT-UHFFFAOYSA-N 0.000 description 2
- 241000209456 Plumbago Species 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 229910052786 argon Inorganic materials 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 239000003153 chemical reaction reagent Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000004070 electrodeposition Methods 0.000 description 2
- 238000005868 electrolysis reaction Methods 0.000 description 2
- 229910052731 fluorine Inorganic materials 0.000 description 2
- 239000011737 fluorine Substances 0.000 description 2
- 230000004907 flux Effects 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- BASFCYQUMIYNBI-UHFFFAOYSA-N platinum Chemical compound [Pt] BASFCYQUMIYNBI-UHFFFAOYSA-N 0.000 description 2
- 238000012913 prioritisation Methods 0.000 description 2
- 239000010453 quartz Substances 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 238000005070 sampling Methods 0.000 description 2
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N silicon dioxide Inorganic materials O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 239000011780 sodium chloride Substances 0.000 description 2
- 238000003756 stirring Methods 0.000 description 2
- 239000006228 supernatant Substances 0.000 description 2
- DNYWZCXLKNTFFI-UHFFFAOYSA-N uranium Chemical compound [U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U] DNYWZCXLKNTFFI-UHFFFAOYSA-N 0.000 description 2
- QGHDLJAZIIFENW-UHFFFAOYSA-N 4-[1,1,1,3,3,3-hexafluoro-2-(4-hydroxy-3-prop-2-enylphenyl)propan-2-yl]-2-prop-2-enylphenol Chemical group C1=C(CC=C)C(O)=CC=C1C(C(F)(F)F)(C(F)(F)F)C1=CC=C(O)C(CC=C)=C1 QGHDLJAZIIFENW-UHFFFAOYSA-N 0.000 description 1
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 description 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 241000906946 Sphingomonas carri Species 0.000 description 1
- ANBBXQWFNXMHLD-UHFFFAOYSA-N aluminum;sodium;oxygen(2-) Chemical compound [O-2].[O-2].[Na+].[Al+3] ANBBXQWFNXMHLD-UHFFFAOYSA-N 0.000 description 1
- 230000003321 amplification Effects 0.000 description 1
- 150000001450 anions Chemical class 0.000 description 1
- 239000007864 aqueous solution Substances 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000005660 chlorination reaction Methods 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- YGANSGVIUGARFR-UHFFFAOYSA-N dipotassium dioxosilane oxo(oxoalumanyloxy)alumane oxygen(2-) Chemical compound [O--].[K+].[K+].O=[Si]=O.O=[Al]O[Al]=O YGANSGVIUGARFR-UHFFFAOYSA-N 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 238000010494 dissociation reaction Methods 0.000 description 1
- 238000005363 electrowinning Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000007499 fusion processing Methods 0.000 description 1
- 230000036571 hydration Effects 0.000 description 1
- 238000006703 hydration reaction Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- XGZVUEUWXADBQD-UHFFFAOYSA-L lithium carbonate Chemical compound [Li+].[Li+].[O-]C([O-])=O XGZVUEUWXADBQD-UHFFFAOYSA-L 0.000 description 1
- 229910052627 muscovite Inorganic materials 0.000 description 1
- 238000003199 nucleic acid amplification method Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000011224 oxide ceramic Substances 0.000 description 1
- 229910052574 oxide ceramic Inorganic materials 0.000 description 1
- 229910052697 platinum Inorganic materials 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 229910052761 rare earth metal Inorganic materials 0.000 description 1
- 150000002910 rare earth metals Chemical class 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 229910001388 sodium aluminate Inorganic materials 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- 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
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Electrolytic Production Of Metals (AREA)
Abstract
The invention discloses and a method for indissolvatingThe molten salt system of metal oxide dry post-treatment is LiF-AlF3A molten salt system, the fluxing salt being Li2CO3Wherein the molar ratio of LiF to AlF3 is 3-4.5: 1, the addition amount of the fluxing salt is 0.1-5% of the total mass of the molten salt. In this system F-Has the function of a buffering agent, and F is used for realizing the melting of oxides by molten salt-The corrosion rate to the associated equipment is reduced to an industrially acceptable level.
Description
Technical field
The invention belongs to fuel assembly behind the irradiation through the non-aqueous solution technical field of treatment scheme again, be specifically related to a kind of molten salt system that is used for the aftertreatment of insoluble metal oxide compound dry method.
Background technology
The dry method post-processing technology is to be grown up by the ANL of the U.S. and Muscovite RIAR, RICT.Russia carries out dry method electrolysis aftertreatment with several kilograms oxide compound spent fuel, proves that this technology is feasible on principle.The U.S. carries out the dry method electrolysis aftertreatment laboratory amplification test of metal spent fuel and also achieves success.At present, the fused salt process is to study one of four kinds of the most active dry method post-processing technologies.The principle of handling the oxide ceramics element be with contain uranium, plutonium are had strong complex performance complex anion salt (like Cl
-, F
-, SO
4 2-Deng) after the fusion, the oxide compound spent fuel is dissolved in this fused salt.The subject matter that this method exists is that the fused complex anion has serious corrodibility to material in the electrolytic system (like container, electrode etc.).
The Chinese nuclear science echnology report of publishing in calendar year 2001 " dry method post-processing technology typical process summary " is (CNIC-01638/38) in the literary composition; Ou Yangyinggen has summarized the molten salt system that multiple fused salt process is adopted; Wherein relatively be typically the metallic lithium reduced oxide electrorefining flow process that laboratory, U.S. Argonne proposes; In the LiCl fused salt, earlier the spent fuel oxide compound is reduced into corresponding metal, and then carries out electrorefining and reclaim the uranium plutonium.But the dissolving power to the oxide compound spent fuel of molten chloride is lower, and the spent fuel amount of fusing in the fused salt is very little, is not enough to be supported in carry out electrowinning in the fused salt.The Russian is oxidized to the sexavalence fusion with the uranium in the MOX powder, plutonium oxide direct chlorination in fused salt, makes the uranium plutonium that Cl is being arranged then
2+ O
2The cathodic reduction galvanic deposit of atmosphere is a uranium plutonium mixed oxide.The chloride oxidation fusion processes of MOX depends on fused salt composition and fused salt working temperature.What this flow process was used the earliest is the LiCl+KCl molten salt system, about 500 ℃ of working temperatures.For improving the fused salt working temperature, change the molten salt system that contains NaCl, CsCl at present.Using NaCl (800 ℃ of fusing points) mainly is in order to improve the working temperature of fused salt, and using CsCl is in order to improve the generation per-cent of sexavalence plutonium.Experiment finds that the interpolation of CsCl can improve the melting degree and the fusing speed of plutonium greatly.However, the recovery of plutonium still is difficult to reach satisfied index.
Summary of the invention
(1) goal of the invention
To the existing defective of molten salt system in the present dry method post-processing technology, the present invention aims to provide a kind of when the oxide compound spent fuel is had certain melting degree, reduces again the corrosive molten salt system of equipment and materials.
(2) technical scheme
A kind of molten salt system based on the aftertreatment of oxide compound spent fuel dry method is LiF-AlF
3Molten salt system, the salt of fluxing is Li
2CO
3, wherein LiF and AlF
3The mole proportioning be 3～4.5: 1, the salt addition of fluxing is 0.1～5% of a fused salt total mass.
As a kind of prioritization scheme, this molten salt system directly uses lithium type sodium aluminum fluoride and LiF, and the mol ratio of lithium type sodium aluminum fluoride and LiF is l: 0.02～l; The salt of fluxing is Li
2CO
3, addition is 0.1～5% of a fused salt total mass.
As a kind of further prioritization scheme, in the process of molten salt system operation, add the LiF that accounts for fused salt total mass 0.1～3%.
(3) invention effect
LiF-AlF
3Or lithium type sodium aluminum fluoride (the sodium aluminum fluoride molecular composition is Na
3AlF
6, have another name called sodium fluoroaluminate, hexafluoro closes sodium aluminate) during fusion, part is dissociated, and contains A1 in the melt
2F
7 -And F
-, under the high temperature, with UO
2Form complex ion.The radius of oxonium ion and fluorion is more or less the same, and fluorion might replace oxonium ion and get into UO
2In the lattice, reaction as follows takes place:
O
2 -Displacement Al
2F
7 -The fluorine of middle fluorine bridged bond makes fused salt further dissociate F
-Come, thereby reaction is moved to right, facilitate UO
2Fusion.In the high-temperature liquid state medium, O
2-Exchange is that mouthful j is contrary.Al
3+Be O
2-The strong cohesiveness acceptor, to O
2-Very strong avidity is arranged, and therefore, molten cryolitic has melting ability preferably to MOX.Al
3+Further with UO
2Dissociation product UOF
2Exchange 0
2-And generation UF
5 -, UF
6 2-Deng.Therefore, at LiF-AlF provided by the present invention
3Molten salt system, F
-Effect with buffer reagent, when realizing fused salt fusion oxide compound, F
-Erosion rate to relevant device is reduced to industrial acceptable degree.
Embodiment
Below by embodiment, technical scheme provided by the present invention is further elaborated.
Embodiment 1
The used reagent of present embodiment is following:
Lithium fluoride (analytical pure; Chemical Reagent Co., Ltd., Sinopharm Group), three hydration ALUMNIUM FLUORIDE (CPs; Chemical Reagent Co., Ltd., Sinopharm Group), Quilonum Retard (analytical pure, Chemical Reagent Co., Ltd., Sinopharm Group), platinum filament (Φ 1mm, 99.9%; Alfa Aesar), uranous oxide (Baotou rare earth emtallurgy research institute), graphite rod (6mm, three high graphite, Beijing three industry graphite companies).
Take by weighing 41g LiF and 42g AlF
3, take by weighing 3g Li
2CO
3In this molten system, LiF and AlF
3The mole proportioning be 3.3:1, salt Li fluxes
2CO
3Addition be that the per-cent of total mass is 3.6%.Salt Li fluxes
2CO
3Play the effect of fluxing with excessive LiF with reduction melt fusing point.
Load weighted salt mixed be placed in the plumbago crucible, crucible is placed in the quartz sleeve, takes by weighing the UO of about 6g
2Powder joins in the dried salt.Logical argon gas transfers to 900 ° of C～950 ° C with the electric furnace preset temp in sleeve, when salt melts, adds the LiF of 0.09g again.Stir melt with stainless steel strip, get supernatant liquid then, analyze UO
2Solubleness.After sampling is accomplished, carry out CV scanning, carry out potentiostatic electrodeposition based on the information of CV scanning gained.The result shows, obtains dendritic settling on the stainless steel cathode, and the content of U is 49 times in the fused salt in this settling.
Embodiment 2
Operation is like embodiment 1.Each drug dosage is following:
LiF 36g and AlF
340g, Li
2CO
30.08g.The add-on of LiF is 1.5g.
Embodiment 3
Operation is like embodiment 1.Each drug dosage is following:
LiF 36g and AlF
326.7g, Li
2CO
33.1g.The add-on of LiF is 2.0g.
Embodiment 4
Experiment condition such as embodiment 1.
Take by weighing the lithium type sodium aluminum fluoride of 73g, the LiF of 12g and the Li of 0.09g
2CO
3Load weighted salt mixed be placed in the plumbago crucible, crucible is placed in the quartz sleeve, takes by weighing the UO of about 12g
2Powder joins in the dried salt.Logical argon gas transfers to 900 ° of C～950 ° C with the electric furnace preset temp in sleeve, when salt melts, adds the LiF of 0.09g again.Stir melt with stainless steel strip, get supernatant liquid then, analyze UO
2Solubleness.After sampling is accomplished, carry out CV scanning, carry out potentiostatic electrodeposition based on the information of CV scanning gained.The result shows that the content of U is 41 times in the fused salt in the dendritic settling of stainless steel cathode.
Embodiment 5
Experiment condition such as embodiment 4.Each drug dosage is following:
Lithium type sodium aluminum fluoride 146g, LiF 12g, Li
2CO
33.2g.The LiF that adds again is 3.2g.
Embodiment 6
Experiment condition such as embodiment 4.Each drug dosage is following:
Lithium type sodium aluminum fluoride 180g, LiF 0.6g, Li
2CO
39.3g.The LiF that adds again is 5.7g.
Obviously those skilled in the art can carry out various modifications and modification and not break away from the spirit and scope of the present invention the present invention.Like this, if of the present invention these revise and modification belongs in the scope of its equivalent technologies of claim of the present invention, then the present invention also is intended to comprise these modifications and modification.
Claims (3)
1. the molten salt system based on the aftertreatment of oxide compound spent fuel dry method is LiF-AlF
3Molten salt system, LiF and AlF
3The mole proportioning be 3～4.5:1; Perhaps this molten salt system directly uses lithium type sodium aluminum fluoride and LiF, and the mol ratio of lithium type sodium aluminum fluoride and LiF is 1:0.02～1;
The salt of fluxing is Li
2CO
3, the salt addition of fluxing is 0.1～5% of a fused salt total mass.
2. the molten salt system based on the aftertreatment of oxide compound spent fuel dry method according to claim 1 is characterized in that: in the process of molten salt system operation, add the LiF that accounts for fused salt total mass 0.1～3%.
3. the molten salt system based on the aftertreatment of oxide compound spent fuel dry method according to claim 1 and 2 is characterized in that: fused salt dissolved temperature is 900 ° of C～950 ° C.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201010555928A CN101994132B (en) | 2010-11-24 | 2010-11-24 | Molten salt system based on oxide spent fuel dry-process aftertreatment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201010555928A CN101994132B (en) | 2010-11-24 | 2010-11-24 | Molten salt system based on oxide spent fuel dry-process aftertreatment |
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| Publication Number | Publication Date |
|---|---|
| CN101994132A CN101994132A (en) | 2011-03-30 |
| CN101994132B true CN101994132B (en) | 2012-10-17 |
Family
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|---|---|---|---|
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN104562089B (en) * | 2014-10-17 | 2017-03-22 | 中国原子能科学研究院 | Method for preparing initial molten salt system in molten salt electrolysis dry after-treatment process |
| CN105132953B (en) * | 2015-07-24 | 2017-11-21 | 中国原子能科学研究院 | A kind of spentnuclear fuel dry method post-processing approach for being used to directly obtain zircaloy fuel |
| JP6839719B2 (en) * | 2016-03-16 | 2021-03-10 | リチャード スコット，イアン | Conversion of used uranium oxide fuel to molten salt reactor fuel |
| CN109637682B (en) * | 2018-11-05 | 2020-09-04 | 中国科学院上海应用物理研究所 | Method for reconstructing molten salt reactor fuel |
| CN110444312B (en) * | 2019-09-03 | 2020-12-29 | 中国科学院近代物理研究所 | Separation of medical isotopes from uranium fission products by dry distillation131Method of I |
-
2010
- 2010-11-24 CN CN201010555928A patent/CN101994132B/en active Active
Non-Patent Citations (2)
| Title |
|---|
| M. Ambrova´et al.Solubilities of lanthanum oxide in fluoride melts Part I. Solubility in M3AlF6 (M = Li, Na, K).《Thermochimica Acta》.2006,第443卷第105-108页. * |
| 邱竹贤.铝电解质体系及其性质.《铝电解》.冶金工业出版社,1995,第46,80-81页. * |
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|---|---|
| CN101994132A (en) | 2011-03-30 |
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