WO2014193469A1 - Separation and recovery of molybdenum values from uranium process distillate - Google Patents
Separation and recovery of molybdenum values from uranium process distillate Download PDFInfo
- Publication number
- WO2014193469A1 WO2014193469A1 PCT/US2013/070001 US2013070001W WO2014193469A1 WO 2014193469 A1 WO2014193469 A1 WO 2014193469A1 US 2013070001 W US2013070001 W US 2013070001W WO 2014193469 A1 WO2014193469 A1 WO 2014193469A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- molybdenum
- uranium
- fluoride
- uranium hexafluoride
- calcium
- Prior art date
Links
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 title claims abstract description 58
- 229910052750 molybdenum Inorganic materials 0.000 title claims abstract description 58
- 239000011733 molybdenum Substances 0.000 title claims abstract description 58
- 238000000034 method Methods 0.000 title claims abstract description 52
- 229910052770 Uranium Inorganic materials 0.000 title claims description 35
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims description 35
- 238000011084 recovery Methods 0.000 title description 6
- 238000000926 separation method Methods 0.000 title description 4
- SANRKQGLYCLAFE-UHFFFAOYSA-H uranium hexafluoride Chemical compound F[U](F)(F)(F)(F)F SANRKQGLYCLAFE-UHFFFAOYSA-H 0.000 claims abstract description 46
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 claims abstract description 33
- 238000004821 distillation Methods 0.000 claims abstract description 26
- PUZPDOWCWNUUKD-UHFFFAOYSA-M sodium fluoride Chemical compound [F-].[Na+] PUZPDOWCWNUUKD-UHFFFAOYSA-M 0.000 claims abstract description 20
- 239000000203 mixture Substances 0.000 claims abstract description 15
- BIOOACNPATUQFW-UHFFFAOYSA-N calcium;dioxido(dioxo)molybdenum Chemical compound [Ca+2].[O-][Mo]([O-])(=O)=O BIOOACNPATUQFW-UHFFFAOYSA-N 0.000 claims abstract description 12
- 239000011775 sodium fluoride Substances 0.000 claims abstract description 10
- 235000013024 sodium fluoride Nutrition 0.000 claims abstract description 10
- 239000011734 sodium Substances 0.000 claims abstract description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 8
- 238000001914 filtration Methods 0.000 claims abstract description 7
- UXVMQQNJUSDDNG-UHFFFAOYSA-L Calcium chloride Chemical compound [Cl-].[Cl-].[Ca+2] UXVMQQNJUSDDNG-UHFFFAOYSA-L 0.000 claims abstract description 6
- 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 claims abstract description 6
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 6
- 239000001110 calcium chloride Substances 0.000 claims abstract description 5
- 229910001628 calcium chloride Inorganic materials 0.000 claims abstract description 5
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 claims description 17
- 238000004519 manufacturing process Methods 0.000 claims description 10
- 239000012535 impurity Substances 0.000 claims description 6
- 159000000007 calcium salts Chemical class 0.000 claims description 5
- KRHYYFGTRYWZRS-UHFFFAOYSA-N Fluorane Chemical compound F KRHYYFGTRYWZRS-UHFFFAOYSA-N 0.000 claims description 4
- KCKICANVXIVOLK-UHFFFAOYSA-L dioxouranium(2+);difluoride Chemical compound [F-].[F-].O=[U+2]=O KCKICANVXIVOLK-UHFFFAOYSA-L 0.000 claims description 2
- 238000001035 drying Methods 0.000 claims description 2
- 230000003301 hydrolyzing effect Effects 0.000 claims 1
- WUKWITHWXAAZEY-UHFFFAOYSA-L calcium difluoride Chemical compound [F-].[F-].[Ca+2] WUKWITHWXAAZEY-UHFFFAOYSA-L 0.000 abstract description 5
- 229910001634 calcium fluoride Inorganic materials 0.000 abstract description 5
- 229910015656 MoOF4 Inorganic materials 0.000 abstract description 3
- 239000000706 filtrate Substances 0.000 abstract description 3
- HCUBBWLKCMNCRQ-UHFFFAOYSA-N oxomolybdenum;tetrahydrofluoride Chemical compound F.F.F.F.[Mo]=O HCUBBWLKCMNCRQ-UHFFFAOYSA-N 0.000 abstract description 3
- 238000000746 purification Methods 0.000 abstract 1
- 239000000243 solution Substances 0.000 description 12
- 150000003839 salts Chemical class 0.000 description 10
- 239000000047 product Substances 0.000 description 8
- 229910052751 metal Inorganic materials 0.000 description 5
- 239000002184 metal Substances 0.000 description 5
- 239000007787 solid Substances 0.000 description 5
- 239000002699 waste material Substances 0.000 description 5
- 239000012467 final product Substances 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000002244 precipitate Substances 0.000 description 3
- 238000004064 recycling Methods 0.000 description 3
- 239000002002 slurry Substances 0.000 description 3
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 2
- 150000001412 amines Chemical class 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- ZCCIPPOKBCJFDN-UHFFFAOYSA-N calcium nitrate Chemical compound [Ca+2].[O-][N+]([O-])=O.[O-][N+]([O-])=O ZCCIPPOKBCJFDN-UHFFFAOYSA-N 0.000 description 2
- 229910052799 carbon Inorganic materials 0.000 description 2
- 239000002131 composite material Substances 0.000 description 2
- 150000001875 compounds Chemical class 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 238000012864 cross contamination Methods 0.000 description 2
- 231100001261 hazardous Toxicity 0.000 description 2
- 230000007062 hydrolysis Effects 0.000 description 2
- 238000006460 hydrolysis reaction Methods 0.000 description 2
- 238000005342 ion exchange Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 150000002739 metals Chemical class 0.000 description 2
- 150000002751 molybdenum Chemical class 0.000 description 2
- 239000012074 organic phase Substances 0.000 description 2
- 238000001556 precipitation Methods 0.000 description 2
- 239000011347 resin Substances 0.000 description 2
- 229920005989 resin Polymers 0.000 description 2
- 239000011684 sodium molybdate Substances 0.000 description 2
- 235000015393 sodium molybdate Nutrition 0.000 description 2
- TVXXNOYZHKPKGW-UHFFFAOYSA-N sodium molybdate (anhydrous) Chemical compound [Na+].[Na+].[O-][Mo]([O-])(=O)=O TVXXNOYZHKPKGW-UHFFFAOYSA-N 0.000 description 2
- 238000000638 solvent extraction Methods 0.000 description 2
- 238000003756 stirring Methods 0.000 description 2
- 229910052719 titanium Inorganic materials 0.000 description 2
- 239000010936 titanium Substances 0.000 description 2
- 229910052720 vanadium Inorganic materials 0.000 description 2
- GPPXJZIENCGNKB-UHFFFAOYSA-N vanadium Chemical compound [V]#[V] GPPXJZIENCGNKB-UHFFFAOYSA-N 0.000 description 2
- 229910000851 Alloy steel Inorganic materials 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 229910000640 Fe alloy Inorganic materials 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 239000003929 acidic solution Substances 0.000 description 1
- 238000007259 addition reaction Methods 0.000 description 1
- 239000000654 additive Substances 0.000 description 1
- 150000001298 alcohols Chemical class 0.000 description 1
- 125000000129 anionic group Chemical group 0.000 description 1
- 239000007767 bonding agent Substances 0.000 description 1
- 238000009933 burial Methods 0.000 description 1
- 229910001622 calcium bromide Inorganic materials 0.000 description 1
- WGEFECGEFUFIQW-UHFFFAOYSA-L calcium dibromide Chemical compound [Ca+2].[Br-].[Br-] WGEFECGEFUFIQW-UHFFFAOYSA-L 0.000 description 1
- AXCZMVOFGPJBDE-UHFFFAOYSA-L calcium dihydroxide Chemical compound [OH-].[OH-].[Ca+2] AXCZMVOFGPJBDE-UHFFFAOYSA-L 0.000 description 1
- 239000000920 calcium hydroxide Substances 0.000 description 1
- 229910001861 calcium hydroxide Inorganic materials 0.000 description 1
- BRPQOXSCLDDYGP-UHFFFAOYSA-N calcium oxide Chemical compound [O-2].[Ca+2] BRPQOXSCLDDYGP-UHFFFAOYSA-N 0.000 description 1
- 239000000292 calcium oxide Substances 0.000 description 1
- ODINCKMPIJJUCX-UHFFFAOYSA-N calcium oxide Inorganic materials [Ca]=O ODINCKMPIJJUCX-UHFFFAOYSA-N 0.000 description 1
- 239000003054 catalyst Substances 0.000 description 1
- 150000001768 cations Chemical class 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000013329 compounding Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000002939 deleterious effect Effects 0.000 description 1
- 210000003298 dental enamel Anatomy 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 239000012153 distilled water Substances 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- ZZUFCTLCJUWOSV-UHFFFAOYSA-N furosemide Chemical compound C1=C(Cl)C(S(=O)(=O)N)=CC(C(O)=O)=C1NCC1=CC=CO1 ZZUFCTLCJUWOSV-UHFFFAOYSA-N 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000003112 inhibitor Substances 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 239000000314 lubricant Substances 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 238000006386 neutralization reaction Methods 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 239000010815 organic waste Substances 0.000 description 1
- HHQFLEDKAVLHOM-UHFFFAOYSA-N oxovanadium;trihydrofluoride Chemical compound F.F.F.[V]=O HHQFLEDKAVLHOM-UHFFFAOYSA-N 0.000 description 1
- 238000005504 petroleum refining Methods 0.000 description 1
- 238000005191 phase separation Methods 0.000 description 1
- 239000000049 pigment Substances 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 230000002028 premature Effects 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 239000003870 refractory metal Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 239000000779 smoke Substances 0.000 description 1
- 235000002639 sodium chloride Nutrition 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000000758 substrate Substances 0.000 description 1
- -1 uranyl fluorides Chemical class 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/04—Halides of uranium
- C01G43/06—Fluorides
- C01G43/063—Hexafluoride (UF6)
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G39/00—Compounds of molybdenum
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2006/00—Physical properties of inorganic compounds
- C01P2006/80—Compositional purity
Definitions
- the present invention relates to a method for recovering the molybdenum and uranium values from process heavy distillate generated during production of nuclear grade uranium hexafluoride. More specifically, the present invention relates to a method for separating the molybdenum and uranium values from such processes into compounds which can be conveniently separated from each other, and from fluoride impurities, in sufficient purity to be sold or recycled for use in manufacturing processes.
- molybdenum amounts of vanadium, titanium, and to a greater extent, molybdenum are vaporized and fed into a boiler still for processing. While the low boiling impurities, i.e. HF, VOF 3 and M0F 6 , are easily removed before the distillation of UF 6 commences, the molybdenum contamination which exists as molybdenum oxytetrafluoride, M0OF 4 , remains. Continuous batch-to-batch refinement of crude uranium hexafluoride results in the accumulation of molybdenum impurity in the high boiler still bottom.
- molybdenum and the molybdenum values are reclaimed as molybdenum salt, and even more preferably, calcium molybdate, which has many commercial uses.
- the present invention provides a method of separating and recovering molybdenum and uranium values from process still high boilers generated during the manufacturing of nuclear grade uranium hexafluoride. Important aspects of the invention reside in the fact that both the molybdenum and uranium values can be recovered in sufficient purity to be recycled or sold. The expense of storage or disposal in a low level nuclear waste burial site is eliminated.
- process still high boilers which comprise UF6 and M0OF 4 are then subjected to distillation at reduced pressure, i.e., at under 90 kPa.
- the distillation is conducted at pressures lower than about 50 kPa, and most preferably, the distillation is conducted at pressures between about 20 kPa and about 35 kPa, e.g., at about 28 kPa (or, about 210 mmHg).
- the distillation is conducted at a suitable temperature for such distillation, e.g., at 60°C for distillation at 210 mmHg).
- the bulk of the UF 6 contained in the high boiling still is removed during this step.
- This solution now contains hydrofluoric acid, the hydrolyzed molybdenum, and any remaining uranium as uranyl fluoride, UO 2 F 2 .
- one objective of the present invention is to provide for a process that results in the isolation of the molybdenum value substantially free of uranium and containing a minimal quantity of fluoride, the hydrolyzed solution is reacted with sodium hydroxide to precipitate remaining uranium as the insoluble salt, sodium diuranate, Na 2 U 2 0 7 and most of the fluoride, preferably at least 95%, as sodium fluoride, NaF.
- the molybdenum remains in solution as the soluble salt, sodium molybdate, a 2 Mo0 4 .
- the molybdenum can be recovered by treating the liquor from the uranium and fluoride
- the isolated salt contains less than about 300 ppm uranium such that the salt can be disposed of safely as non- hazardous and/or non-nuclear waste. Even more preferably, the isolated salt contains less than 10, or even 1 ppm uranium, so that it is readily saleable and usable in a number of commercial applications.
- the uranium values contained in the sodium diuranate salt/sodium fluoride mixture can recovered and recycled by using standard process chemistry known to those skilled in the art.
- process still high boilers consisting of uranium hexafluoride, UF 6 and molybdenum oxytetrafluoride, M0OF 4 are subjected to distillation at 60°C and 210 mm Hg to remove the bulk amount of the uranium hexafluoride contained in the high boiler mixture.
- the residue remaining after the distillation is subjected to hydrolysis using water.
- the quantity of water is not critical but should be sufficient to dissolve the solids. Typically., a mass ratio of 1 : 1 solids to water is adequate.
- the resulting highly acidic solution is treated with a 20 wt% solution of sodium hydroxide until the pH is 7.5 or higher.
- the concentration of sodium hydroxide is not critical. Solutions ranging from 5% to 50% can be used. Dilute concentrations require larger reaction vessels and can add to the amount of sodium fluoride which contaminates the final molybdenum product as sodium fluoride has a slight solubility in water, while concentrations can require the use of additional cooling equipment to compensate for the heat generated during the neutralization step.
- the addition of sodium hydroxide precipitates any remaining uranium as the insoluble salt, sodium diuranate, Na 2 U 2 0 7 . Also precipitated during this step is at least 95% of the contained fluoride ion as the partially soluble salt, sodium fluoride, NaF. These salts are removed from the liquor which contains the molybdenum values by standard filtration techniques. These solids can be used as is or dried prior to recycling into a typical uranium recovery process known to those skilled in the art.
- the filtrate from the above filtration, containing the molybdenum values is reacted with a 20 wt% solution of calcium chloride.
- calcium salts can be used in this step, e.g., calcium bromide, calcium nitrate, calcium hydroxide, calcium oxide and the like, calcium chloride is preferred for economic reasons and a favorable reaction rate.
- the concentration of the calcium chloride solution is not critical and can range from 5% to as high as 70%. Lower concentrations generate additional aqueous waste which must be disposed and higher concentration can lead to thick slurries which are difficult to stir and thus may affect the final purity of the desired calcium salt, calcium molybdate, CaMoC .
- the addition reaction is carried out at ambient conditions, e.g., at around 25°C, as this is the most economical condition for the process.
- the reaction is complete and the precipitated calcium molybdate can be isolated by standard filtration techniques known to those skilled in the art.
- the product is conveniently dried by heating at 100°C.
- This product contains a small quantity of fluoride as calcium fluoride, CaF 2 .
- the calcium molybdate is suitable for use in the applications described above.
- This example details the process for removal of uranium hexafluoride from the high boiler composite sample.
- a nickel cylinder containing 1289.4 g of high boiler components was subjected to distillation.
- the cylinder was heated to 60°C and the vacuum maintained between 200-220 mm Hg during the distillation. After 3 hours of distillation there was no observable change in weight of the cylinder. The distillation was terminated and the product cylinder weighed. A total of 213.3 g of distillate was obtained which consisted of pure UF 6 . Analysis of this distillate fraction indicated that no molybdenum contamination of the distillate product has occurred. The molybdenum value was ⁇ 1 ppm.
- the high boiler composite contained 16.55% recoverable UF 6 .
- Example 1 This example is presented to document the UF6 remaining after the distillation described in Example 1.
- a 25 g sample of liquid obtained from Example 1 was analyzed for residual uranium. It was determined that the uranium content was equal to 2340 ppm.
- This example illustrates the process for removal of the residual uranium and fluoride from the hydro lyzed distillate produced after performing the distillation described in Example 1.
- This example illustrates the process for producing and isolating the molybdenum values as calcium molybdate, CaMo0 4 .
- This Example illustrates the use of 40 wt% NaOH and follows the procedures described in Examples 3 and 4, which takes this process to the final product, CaMo0 4 .
- This example illustrates the use of 50 wt% NaOH and follows the procedures described in Examples 3 and 4 to isolate the final product CaMoOF 4 .
- a uranium concentration was determined and found to be U ⁇ 1.6ppm.
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Inorganic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Removal Of Specific Substances (AREA)
Priority Applications (5)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| EP13886008.5A EP2920115A4 (en) | 2012-11-16 | 2013-11-14 | SEPARATION AND RECOVERY OF MOLYBDEN VALUES FROM A UREA PROCESSING DISTILLATE |
| CA2890310A CA2890310A1 (en) | 2012-11-16 | 2013-11-14 | Separation and recovery of molybdenum values from uranium process distillate |
| JP2015542761A JP6333836B2 (ja) | 2012-11-16 | 2013-11-14 | ウラン処理工程の留出物からの有価モリブデン成分の分離及び回収 |
| CN201380059990.XA CN104870370A (zh) | 2012-11-16 | 2013-11-14 | 钼值从铀过程馏出物的分离和回收 |
| IN3757DEN2015 IN2015DN03757A (en:Method) | 2012-11-16 | 2013-11-14 |
Applications Claiming Priority (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US201261727580P | 2012-11-16 | 2012-11-16 | |
| US61/727,580 | 2012-11-16 | ||
| US14/079,351 | 2013-11-13 | ||
| US14/079,351 US9567237B2 (en) | 2012-11-16 | 2013-11-13 | Separation and recovery of molybdenum values from uranium process distillate |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO2014193469A1 true WO2014193469A1 (en) | 2014-12-04 |
Family
ID=50728129
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/US2013/070001 WO2014193469A1 (en) | 2012-11-16 | 2013-11-14 | Separation and recovery of molybdenum values from uranium process distillate |
Country Status (7)
| Country | Link |
|---|---|
| US (1) | US9567237B2 (en:Method) |
| EP (1) | EP2920115A4 (en:Method) |
| JP (1) | JP6333836B2 (en:Method) |
| CN (1) | CN104870370A (en:Method) |
| CA (1) | CA2890310A1 (en:Method) |
| IN (1) | IN2015DN03757A (en:Method) |
| WO (1) | WO2014193469A1 (en:Method) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015051127A1 (en) * | 2013-10-02 | 2015-04-09 | Mestena Operating, Ltd. | Methods and apparatus for recovering molybdenum in uranium in-situ recovery process |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3046089A (en) * | 1961-02-08 | 1962-07-24 | Martin J Steindler | Process of treating uranium hexafluoride and plutonium hexafluoride mixtures with sulfur tetrafluoride to separate same |
| US3383183A (en) * | 1964-10-05 | 1968-05-14 | Atomic Energy Authority Uk | Processing of metal fluorides including uranium hexafluoride with anhydrous hydrogenfluoride |
| US3806579A (en) * | 1970-04-08 | 1974-04-23 | Commissariat Energie Atomique | Method of purification of uranium hexafluoride |
| US4584184A (en) * | 1984-05-21 | 1986-04-22 | Allied Corporation | Separation and recovery of molybdenum values from uranium process waste |
| US5431891A (en) | 1992-02-11 | 1995-07-11 | Companie Generale Des Matieres Nucleaires | Process for the recovery and purification of a metal alloy based on highly enriched uranium |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE562286A (en:Method) | ||||
| GB858161A (en) | 1958-04-10 | 1961-01-11 | Allied Chem | Purification of uranium hexafluoride |
| US2953431A (en) * | 1958-04-10 | 1960-09-20 | Allied Chem | Purification of uf6 |
| GB893320A (en) | 1960-02-10 | 1962-04-04 | Allied Chem | Purification of uranium ore concentrates |
| NL267653A (en:Method) | 1960-08-03 | 1900-01-01 | ||
| US3790658A (en) | 1970-05-15 | 1974-02-05 | Union Carbide Corp | Purification process for recovering uranium from an acidic aqueous solution by ph control |
| US4011296A (en) | 1975-05-27 | 1977-03-08 | General Electric Company | Irradiated fuel reprocessing |
| US4092399A (en) | 1976-12-01 | 1978-05-30 | Atlantic Richfield Company | Recovery of uranium from carbonate leach solutions |
| US4304757A (en) | 1977-08-04 | 1981-12-08 | Mobil Oil Corporation | Method of controlling the molybdenum content of uranium yellowcake |
| US4199551A (en) | 1978-01-13 | 1980-04-22 | Amax Inc. | Recovery of molybdenum and uranium from activated charcoal containing molybdenum and residual uranium |
| US4366126A (en) | 1979-12-14 | 1982-12-28 | Union Carbide Corporation | Removal of molybdenum from uranium solutions |
| FR2484989A1 (fr) | 1980-06-19 | 1981-12-24 | Pechiney Ugine Kuhlmann Uran | Procede de separation selective de l'uranium et du molybdene contenus dans un solvant amine |
| FR2491451A1 (fr) | 1980-10-03 | 1982-04-09 | Cogema | Procede de recuperation separee du molybdene et du vanadium |
| US4407781A (en) | 1981-03-05 | 1983-10-04 | Westinghouse Electric Corp. | Method of separating molybdenum from uranium |
| US4393028A (en) | 1981-06-12 | 1983-07-12 | Wyoming Mineral Corporation | Method of removing uranium from a slurry containing molybdenum |
| US4375452A (en) | 1981-10-15 | 1983-03-01 | Mobil Oil Corporation | Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange |
| FR2575585B1 (fr) | 1984-12-28 | 1987-01-30 | Commissariat Energie Atomique | Procede de recuperation de molybdene-99 a partir d'une cible d'alliage d'uranium irradie |
| JPS61281019A (ja) | 1985-06-04 | 1986-12-11 | Mitsubishi Metal Corp | 六フツ化ウランを二酸化ウランに変換する方法 |
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| CA2025165C (en) | 1990-09-13 | 1997-11-25 | Edmond K. Lam | Removal of molybdenum from uranium-bearing solutions |
| US5666639A (en) | 1994-06-07 | 1997-09-09 | Iti Group Llc | CRISLA process and apparatus |
| GB9607901D0 (en) | 1996-04-17 | 1996-06-19 | British Nuclear Fuels Plc | Metal flourides separation |
| US6352677B1 (en) | 1996-06-04 | 2002-03-05 | Alliedsignal, Inc. | Process to produce commercial grade anhydrous hydrogen fluoride (AHF) and uranium oxide from the delfuorination of uranium hexafluoride (UF6) |
| GB9900836D0 (en) | 1999-01-15 | 1999-03-31 | British Nuclear Fuels Plc | Improvements in and relating to processing materials |
| JP4022608B2 (ja) | 2004-07-30 | 2007-12-19 | 独立行政法人 日本原子力研究開発機構 | 分留法を用いるフッ化物揮発法による再処理方法 |
| US20090068086A1 (en) | 2007-09-07 | 2009-03-12 | Richard Allen Hogle | Method and apparatus for the production of high purity tungsten hexafluoride |
| FR2947663B1 (fr) | 2009-07-02 | 2011-07-29 | Areva Nc | Procede ameliore de traitement de combustibles nucleaires uses |
| FR2954354B1 (fr) | 2009-12-22 | 2012-01-13 | Commissariat Energie Atomique | Procede de purification de l'uranium d'un concentre d'uranium naturel |
| FI122274B (fi) | 2010-02-02 | 2011-11-15 | Outotec Oyj | Uuttoprosessi |
| CN102153143B (zh) | 2011-04-15 | 2013-01-02 | 中核北方核燃料元件有限公司 | 一种重铀酸铵的制备工艺方法及装置 |
| CN103894155B (zh) | 2014-04-22 | 2016-04-27 | 中国工程物理研究院核物理与化学研究所 | 一种用于水体中铀提取的离子筛及其制备方法 |
-
2013
- 2013-11-13 US US14/079,351 patent/US9567237B2/en not_active Expired - Fee Related
- 2013-11-14 CA CA2890310A patent/CA2890310A1/en not_active Abandoned
- 2013-11-14 CN CN201380059990.XA patent/CN104870370A/zh active Pending
- 2013-11-14 EP EP13886008.5A patent/EP2920115A4/en not_active Withdrawn
- 2013-11-14 IN IN3757DEN2015 patent/IN2015DN03757A/en unknown
- 2013-11-14 JP JP2015542761A patent/JP6333836B2/ja not_active Expired - Fee Related
- 2013-11-14 WO PCT/US2013/070001 patent/WO2014193469A1/en active Application Filing
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3046089A (en) * | 1961-02-08 | 1962-07-24 | Martin J Steindler | Process of treating uranium hexafluoride and plutonium hexafluoride mixtures with sulfur tetrafluoride to separate same |
| US3383183A (en) * | 1964-10-05 | 1968-05-14 | Atomic Energy Authority Uk | Processing of metal fluorides including uranium hexafluoride with anhydrous hydrogenfluoride |
| US3806579A (en) * | 1970-04-08 | 1974-04-23 | Commissariat Energie Atomique | Method of purification of uranium hexafluoride |
| US4584184A (en) * | 1984-05-21 | 1986-04-22 | Allied Corporation | Separation and recovery of molybdenum values from uranium process waste |
| US5431891A (en) | 1992-02-11 | 1995-07-11 | Companie Generale Des Matieres Nucleaires | Process for the recovery and purification of a metal alloy based on highly enriched uranium |
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Also Published As
| Publication number | Publication date |
|---|---|
| US20140140905A1 (en) | 2014-05-22 |
| US9567237B2 (en) | 2017-02-14 |
| EP2920115A1 (en) | 2015-09-23 |
| CN104870370A (zh) | 2015-08-26 |
| CA2890310A1 (en) | 2014-12-04 |
| EP2920115A4 (en) | 2016-06-22 |
| JP2016501174A (ja) | 2016-01-18 |
| IN2015DN03757A (en:Method) | 2015-10-02 |
| JP6333836B2 (ja) | 2018-05-30 |
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