US2766110A - Method of refining uranium - Google Patents
Method of refining uranium Download PDFInfo
- Publication number
- US2766110A US2766110A US525601A US52560144A US2766110A US 2766110 A US2766110 A US 2766110A US 525601 A US525601 A US 525601A US 52560144 A US52560144 A US 52560144A US 2766110 A US2766110 A US 2766110A
- Authority
- US
- United States
- Prior art keywords
- uranium
- bath
- fused
- refining
- powder
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
- 229910052770 Uranium Inorganic materials 0.000 title claims description 51
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims description 50
- 238000000034 method Methods 0.000 title claims description 23
- 238000007670 refining Methods 0.000 title claims description 12
- 238000010438 heat treatment Methods 0.000 claims description 7
- WDIHJSXYQDMJHN-UHFFFAOYSA-L barium chloride Chemical compound [Cl-].[Cl-].[Ba+2] WDIHJSXYQDMJHN-UHFFFAOYSA-L 0.000 claims description 4
- 229910001626 barium chloride Inorganic materials 0.000 claims description 4
- VBKNTGMWIPUCRF-UHFFFAOYSA-M potassium;fluoride;hydrofluoride Chemical compound F.[F-].[K+] VBKNTGMWIPUCRF-UHFFFAOYSA-M 0.000 claims description 2
- 150000003839 salts Chemical class 0.000 description 15
- 239000000843 powder Substances 0.000 description 12
- 239000012535 impurity Substances 0.000 description 10
- 239000000203 mixture Substances 0.000 description 8
- 239000002253 acid Substances 0.000 description 7
- -1 uranium halide Chemical class 0.000 description 7
- 229910052751 metal Inorganic materials 0.000 description 5
- 239000002184 metal Substances 0.000 description 5
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 4
- 238000005868 electrolysis reaction Methods 0.000 description 4
- 230000008018 melting Effects 0.000 description 4
- 238000002844 melting Methods 0.000 description 4
- 238000005406 washing Methods 0.000 description 4
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 description 3
- ZLMJMSJWJFRBEC-UHFFFAOYSA-N Potassium Chemical compound [K] ZLMJMSJWJFRBEC-UHFFFAOYSA-N 0.000 description 3
- 238000000227 grinding Methods 0.000 description 3
- 239000011261 inert gas Substances 0.000 description 3
- 239000011591 potassium Substances 0.000 description 3
- 229910052700 potassium Inorganic materials 0.000 description 3
- 238000005245 sintering Methods 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 229910052799 carbon Inorganic materials 0.000 description 2
- 150000004820 halides Chemical class 0.000 description 2
- 150000002739 metals Chemical class 0.000 description 2
- 239000011780 sodium chloride Substances 0.000 description 2
- PUZPDOWCWNUUKD-UHFFFAOYSA-M sodium fluoride Chemical compound [F-].[Na+] PUZPDOWCWNUUKD-UHFFFAOYSA-M 0.000 description 2
- OYPRJOBELJOOCE-UHFFFAOYSA-N Calcium Chemical compound [Ca] OYPRJOBELJOOCE-UHFFFAOYSA-N 0.000 description 1
- UXVMQQNJUSDDNG-UHFFFAOYSA-L Calcium chloride Chemical compound [Cl-].[Cl-].[Ca+2] UXVMQQNJUSDDNG-UHFFFAOYSA-L 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
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 239000003513 alkali Substances 0.000 description 1
- 229910052788 barium Inorganic materials 0.000 description 1
- DSAJWYNOEDNPEQ-UHFFFAOYSA-N barium atom Chemical compound [Ba] DSAJWYNOEDNPEQ-UHFFFAOYSA-N 0.000 description 1
- OYLGJCQECKOTOL-UHFFFAOYSA-L barium fluoride Chemical compound [F-].[F-].[Ba+2] OYLGJCQECKOTOL-UHFFFAOYSA-L 0.000 description 1
- 229910001632 barium fluoride Inorganic materials 0.000 description 1
- 229910052791 calcium Inorganic materials 0.000 description 1
- 239000011575 calcium Substances 0.000 description 1
- 239000001110 calcium chloride Substances 0.000 description 1
- 229910001628 calcium chloride Inorganic materials 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 238000004070 electrodeposition Methods 0.000 description 1
- 239000011876 fused mixture Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- ORUIBWPALBXDOA-UHFFFAOYSA-L magnesium fluoride Chemical compound [F-].[F-].[Mg+2] ORUIBWPALBXDOA-UHFFFAOYSA-L 0.000 description 1
- 229910001635 magnesium fluoride Inorganic materials 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000011946 reduction process Methods 0.000 description 1
- 239000002893 slag Substances 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011775 sodium fluoride Substances 0.000 description 1
- 235000013024 sodium fluoride Nutrition 0.000 description 1
- 238000003756 stirring Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 150000003671 uranium compounds Chemical class 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
- 230000008016 vaporization Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Images
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0286—Obtaining thorium, uranium, or other actinides obtaining uranium refining, melting, remelting, working up uranium
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
Definitions
- This invention relates -to the refining of uranium and more particularly to a method of refining and purifying uranium powder produced by electrolysis or produced by other reduction processes.
- Uranium metal prepared by electrodeposition from a fused salt bath is generally in the form of powder containing more or less impurities including uranium oxide, metals, and salts from the fused bath.
- powdered uranium may be refined and puried by a series of crushing, Washing, grinding, drying, sintering and fusing operations to obtain a body of coalescent uranium suitable for commercial uses.
- impure uranium may be refined and purified -by treatment at high temperatures in a fused salt bath to remove oxides, salts and any other impurities.
- An alkali acid fluoride bath such as potassium acid
- I-t is still another object of this invention to provide a fused salt bath for refining impure uranium lat temperatures above the melting point of uranium.
- uranium powder such as that produced eleetrolytically nited States Patent- Pice in accordance with the disclosure of said copending application, is rened in a fused salt bath at temperatures above the melting point of uranium.
- the uranium to be refined may be the electrodeposited powder, as mentioned above, or it may be uranium produced by other methods and/or uranium partially -rened by crushing, Washing, sintering, fusing or similar operations.
- the fused salt bath may include sodium chloride, NaCl, calcium chloride, CaClz, barium chloride, VBaClz, sodium fluoride, Nal?, calcium uoride, CaFz, barium fluoride, BaFz, or magnesium fluoride, MgFz, and the like, alone or in combination.
- a particularly suitable bath conttt-ins a potassium acid fluoride, such as KHFz, in combination with another halide, such as barium chloride, BaClz.
- the ratio of the acid uoride to the halide is not critical except that the mixture should be such as to be fused and remain molten lat temperatures of the order of l000 to l200 C.
- the temperature of the ba-th should be maintained -at about 1100 to 1200 C. during the refining operation by any suitable means such Aas by resistance heating or by high frequency induction heating in .the event that the heat capacity of the bath is insufhcient 'to maintain a temperature above the melting point of uranium long enough for the impurities to be separated from the uranium.
- the preferred method of this invention includes the steps of heating .the mixture of salts until a fused bath having a temperature of 1000" to 1100 C. is attained, adding the impure uranium -to be rened to the fused bath, raising the temperature of the fused mixture to approximately 1200 C., and maintaining said temperature for about ten minutes while stirring the mixture with a carbon rod.
- Similar methods such as adding the fused salts to the impure uranium, or fusing the sal-ts and uranium together in an inert gas or in vacuum, may also be used.
- the described Atreatment apparently refines the impure uranium by vaporizing certain impurities and by converting other impurities into products which vaporize and/or products which dissolve or remain in the bath mixture. While the refining operation may be conducted successfully in air, the presence of a circulated inert gas or a vacuum is advantageous to carry away the volatile impurities including volatile uorides.
- the particles of uranium fuse and coalesce in the salt bath to form pure uranium in coalescent form.
- the fused uranium may be allowed to solidify in the bottom of the crucible under a layer of slag and a layer of salt, and may be subsequently recovered by breaking open the crucible.
- the fused uranium may also be recovered by being tapped from the bottom of the Crucible and cast in a suitable m-old or molds.
- uranium in either the powder form or a dense form may be easily refined to produce fused uranium in coalescen-t condition free of oxide and salt impurities and free of metals such as metallic sodium.
- the novel method disclosed is particularly economical since it eliminates crushing, washing, grinding, sintering, and simil-ar steps, and eliminates the losses inherent in such steps.
- the method of refining uranium which comprises the steps of preparing a fused bath containing essentially a potassium acid uoride and barium chloride, heating 3 4 said 'bath to a temperature of approximately 1100 C. to References Cited in the le of this patent 1200 C., -adding impure uranium to said fused bath, and UNITED STATES PATENTS collecting substantially pure uranium in coalescent form under Said bath 1,180,435 RObSOll Apr. 25, 1916 3.
- the method of refining uranium which comprises 230865 Great Bmtam Dec' 10 1925 the steps of preparing a fused bath containing essentially 15 OTHER REFERENCES a mixture of a potassium acid liu-oride and barium Chlo; Goggin. Cronin, Fogg, James: Industrial and Em ride, heating said -batli -to a temperature of about 1100 gineering Chemistry, Fell 1926 pp. 114 116 fo 1200 C addmg 'impure Uranium Powder Produced w. Kroll; Zeitschrift fr Metauischen, Feb. 1936,
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- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Geology (AREA)
- Manufacturing & Machinery (AREA)
- Environmental & Geological Engineering (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Electrolytic Production Of Metals (AREA)
Description
VOct. 9, 1956 l G. MEISTER V'2,755,110
METHOD OF REFINING URANIUM Filed March 8, 1944 /NRT GAS FEED CARBON gli l g ROD ;;:l f F055@ JT/RRER JAU- BATH muc/BLE g /-cAA 0v/v E HIGH FREQUENCY HfA TER cof/ E E mlmll URAA//UMMEML :Hi:
WATER COOL/N6 CO/L FOI? PLA TE l VACUUM EXHAUST TUBE IN V EN TOR. GEORGE M15/5775A A TTORNEY.
METHOD OF REFINING URANIUM George Meister, Newark, N. J., assignor to the United States of America as represented by the United States Atomic Energy Commission Application March s, 1944, serial No. 525,601
' 3 claims. (c1. 'ls-sal) This invention relates -to the refining of uranium and more particularly to a method of refining and purifying uranium powder produced by electrolysis or produced by other reduction processes.
Methods and apparatus for the recovery of uranium by the electrolysis of uranium compounds in a fused salt bath are disclosed in copending application Serial No. 478,270, led March 6, 1943, by William C. Lilliendahl et al., now United States Letters Patent N-o. 2,690,421, issued September 28, 1954. Brieliy, the method thereof includes the electrolysis of a uranium halide in a fused salt bath in which uranium is deposited on a cathode in the -form of a powder, the rening of the uranium powder to free it of soluble impurities by grinding and washing operati-ons, and finally the compression of the uranium powder into a slug or button. The present invention relates to improvements lin methods of refining uranium, particularly electrolytically deposited uranium powder, such as the uranium deposits produced by the methods and apparatus of said application.
Uranium metal prepared by electrodeposition from a fused salt bath is generally in the form of powder containing more or less impurities including uranium oxide, metals, and salts from the fused bath. As set forth in the above-mentioned application, such powdered uranium may be refined and puried by a series of crushing, Washing, grinding, drying, sintering and fusing operations to obtain a body of coalescent uranium suitable for commercial uses.
The present invention discloses that impure uranium may be refined and purified -by treatment at high temperatures in a fused salt bath to remove oxides, salts and any other impurities. An alkali acid fluoride bath, such as potassium acid |fluoride 'is found to be particularly effective.
It is the object of this Iinvention to provide a method of relining and purifying uranium by separating the impurities from the uranium while simultaneously fusing the pure metal s-o produced.
It is an object of this invention to provide a method gf fusing uranium powder to obtain uranium in coalescent or-m.
It is another object of this invention to provide a method using a fused salt bath for purifying and fusing uranium powder.
I-t is still another object of this invention to provide a fused salt bath for refining impure uranium lat temperatures above the melting point of uranium.
Other objects and advantages of the invention will be readily apparent to those skilled in the art from the following description of preferred methods and bath compositions embodying the invention.
The drawing is illustrative of apparatus which may be employed in practicing the method which constitutes the subject matter of the present invention.
According to the method of the present invention, uranium powder, such as that produced eleetrolytically nited States Patent- Pice in accordance With the disclosure of said copending application, is rened in a fused salt bath at temperatures above the melting point of uranium. The uranium to be refined may be the electrodeposited powder, as mentioned above, or it may be uranium produced by other methods and/or uranium partially -rened by crushing, Washing, sintering, fusing or similar operations. The fused salt bath may include sodium chloride, NaCl, calcium chloride, CaClz, barium chloride, VBaClz, sodium fluoride, Nal?, calcium uoride, CaFz, barium fluoride, BaFz, or magnesium fluoride, MgFz, and the like, alone or in combination. A particularly suitable bath conttt-ins a potassium acid fluoride, such as KHFz, in combination with another halide, such as barium chloride, BaClz. The ratio of the acid uoride to the halide is not critical except that the mixture should be such as to be fused and remain molten lat temperatures of the order of l000 to l200 C. in order to be molten at temperatures above the melting point of uranium metal. An acid uoride bath appears to be more satisfactory than a straight fluoride bath, possibly because of better heating and because the acid uoride more readily dissolves the oxide impurities. The temperature of the ba-th should be maintained -at about 1100 to 1200 C. during the refining operation by any suitable means such Aas by resistance heating or by high frequency induction heating in .the event that the heat capacity of the bath is insufhcient 'to maintain a temperature above the melting point of uranium long enough for the impurities to be separated from the uranium.
The preferred method of this invention includes the steps of heating .the mixture of salts until a fused bath having a temperature of 1000" to 1100 C. is attained, adding the impure uranium -to be rened to the fused bath, raising the temperature of the fused mixture to approximately 1200 C., and maintaining said temperature for about ten minutes while stirring the mixture with a carbon rod. Similar methods, such as adding the fused salts to the impure uranium, or fusing the sal-ts and uranium together in an inert gas or in vacuum, may also be used. 'The described Atreatment apparently refines the impure uranium by vaporizing certain impurities and by converting other impurities into products which vaporize and/or products which dissolve or remain in the bath mixture. While the refining operation may be conducted successfully in air, the presence of a circulated inert gas or a vacuum is advantageous to carry away the volatile impurities including volatile uorides. The particles of uranium fuse and coalesce in the salt bath to form pure uranium in coalescent form. The fused uranium may be allowed to solidify in the bottom of the crucible under a layer of slag and a layer of salt, and may be subsequently recovered by breaking open the crucible. The fused uranium may also be recovered by being tapped from the bottom of the Crucible and cast in a suitable m-old or molds.
By use of the methods and compositions set forth above, uranium in either the powder form or a dense form may be easily refined to produce fused uranium in coalescen-t condition free of oxide and salt impurities and free of metals such as metallic sodium. The novel method disclosed is particularly economical since it eliminates crushing, washing, grinding, sintering, and simil-ar steps, and eliminates the losses inherent in such steps.
Various changes and substitutions may be made in the methods and compositi-ons described without departing from the spirit and scope of my invention as defined in the following claims.
I claim:
1. The method of refining uranium which comprises the steps of preparing a fused bath containing essentially a potassium acid uoride and barium chloride, heating 3 4 said 'bath to a temperature of approximately 1100 C. to References Cited in the le of this patent 1200 C., -adding impure uranium to said fused bath, and UNITED STATES PATENTS collecting substantially pure uranium in coalescent form under Said bath 1,180,435 RObSOll Apr. 25, 1916 3. The method of refining uranium which comprises 230865 Great Bmtam Dec' 10 1925 the steps of preparing a fused bath containing essentially 15 OTHER REFERENCES a mixture of a potassium acid liu-oride and barium Chlo; Goggin. Cronin, Fogg, James: Industrial and Em ride, heating said -batli -to a temperature of about 1100 gineering Chemistry, Fell 1926 pp. 114 116 fo 1200 C addmg 'impure Uranium Powder Produced w. Kroll; Zeitschrift fr Metaukunde, Feb. 1936,
by electrolysis to said bath while maintaining a ow of p an inert gas over the surface of said bath, and collecting 20 substantially pure uranium in coalescen't for-rn under said bath.
Claims (1)
1. THE METHOD OF REFINING URANIUM WHICH COMPRISES THE STEPS OF PREPARING A FUSED BATH CONTAINING ESSENTIALLY A POTASSIUM ACID FLUORIDE AND BARIUM CHLORIDE, HEATING SAID BATH TO A TEMPERATURE OF APPROXIMATELY 1100* C. TO 1200* C., ADDING IMPURE URANIUM TO SAID FUSED BATH, AND COLLECTING SUBSTANTIALLY PURE URANIUM IN COALESCENT FORM UNDER SAID BATH.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US525601A US2766110A (en) | 1944-03-08 | 1944-03-08 | Method of refining uranium |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US525601A US2766110A (en) | 1944-03-08 | 1944-03-08 | Method of refining uranium |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US2766110A true US2766110A (en) | 1956-10-09 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US525601A Expired - Lifetime US2766110A (en) | 1944-03-08 | 1944-03-08 | Method of refining uranium |
Country Status (1)
| Country | Link |
|---|---|
| US (1) | US2766110A (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2852246A (en) * | 1956-02-27 | 1958-09-16 | Janco Nathan | Vacuum degassing apparatus |
| US2949390A (en) * | 1957-08-07 | 1960-08-16 | Harold M Feder | Method of protecting tantalum crucibles against reaction with molten uranium |
| US2990273A (en) * | 1959-08-28 | 1961-06-27 | Chiotti Premo | Uranium recovery from metallic masses |
| US2995439A (en) * | 1959-02-02 | 1961-08-08 | Union Carbide Corp | Preparation of high purity chromium and other metals |
| US3401023A (en) * | 1964-07-29 | 1968-09-10 | Nat Res Dev | Crystal melt-growth process wherein the melt surface is covered with an inert liquid |
| US3410679A (en) * | 1965-07-26 | 1968-11-12 | Tammet Internat | Method of making metal alloys, particularly ferrotitanium alloy |
| US4591382A (en) * | 1980-03-22 | 1986-05-27 | Elliott Guy R B | Process and apparatus for recovering and purifying uranium scrap |
| USH137H (en) | 1985-04-11 | 1986-10-07 | The United States Of America As Represented By The United States Department Of Energy | Process for reducing beta activity in uranium |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US1180435A (en) * | 1912-02-12 | 1916-04-25 | Metallic Smelting And Refining Company | Process of recovering metals. |
| GB230865A (en) * | 1924-03-17 | 1925-12-10 | Westinghouse Lamp Co | Improvements relating to the manufacture of fused uranium |
| US1568685A (en) * | 1923-03-02 | 1926-01-05 | Gen Electric | Purification of highly-oxidizable metals |
| US1814721A (en) * | 1925-01-13 | 1931-07-14 | Westinghouse Lamp Co | Preparation of ductile uranium |
| US1841599A (en) * | 1930-01-09 | 1932-01-19 | Refined Steel Products Company | Method of treating nonferrous metals |
| US1861625A (en) * | 1929-03-30 | 1932-06-07 | Westinghouse Lamp Co | Method of producing rare metals by electrolysis |
| US1968984A (en) * | 1931-12-23 | 1934-08-07 | Dow Chemical Co | Method and flux for autogenously welding magnesium and its alloys |
| US2170863A (en) * | 1936-06-06 | 1939-08-29 | Junker Erich | Process for melting up light metal scrap |
| US2261905A (en) * | 1941-04-25 | 1941-11-04 | Dow Chemical Co | Method of alloying magnesium with manganese |
-
1944
- 1944-03-08 US US525601A patent/US2766110A/en not_active Expired - Lifetime
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US1180435A (en) * | 1912-02-12 | 1916-04-25 | Metallic Smelting And Refining Company | Process of recovering metals. |
| US1568685A (en) * | 1923-03-02 | 1926-01-05 | Gen Electric | Purification of highly-oxidizable metals |
| GB230865A (en) * | 1924-03-17 | 1925-12-10 | Westinghouse Lamp Co | Improvements relating to the manufacture of fused uranium |
| US1814721A (en) * | 1925-01-13 | 1931-07-14 | Westinghouse Lamp Co | Preparation of ductile uranium |
| US1861625A (en) * | 1929-03-30 | 1932-06-07 | Westinghouse Lamp Co | Method of producing rare metals by electrolysis |
| US1841599A (en) * | 1930-01-09 | 1932-01-19 | Refined Steel Products Company | Method of treating nonferrous metals |
| US1968984A (en) * | 1931-12-23 | 1934-08-07 | Dow Chemical Co | Method and flux for autogenously welding magnesium and its alloys |
| US2170863A (en) * | 1936-06-06 | 1939-08-29 | Junker Erich | Process for melting up light metal scrap |
| US2261905A (en) * | 1941-04-25 | 1941-11-04 | Dow Chemical Co | Method of alloying magnesium with manganese |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2852246A (en) * | 1956-02-27 | 1958-09-16 | Janco Nathan | Vacuum degassing apparatus |
| US2949390A (en) * | 1957-08-07 | 1960-08-16 | Harold M Feder | Method of protecting tantalum crucibles against reaction with molten uranium |
| US2995439A (en) * | 1959-02-02 | 1961-08-08 | Union Carbide Corp | Preparation of high purity chromium and other metals |
| US2990273A (en) * | 1959-08-28 | 1961-06-27 | Chiotti Premo | Uranium recovery from metallic masses |
| US3401023A (en) * | 1964-07-29 | 1968-09-10 | Nat Res Dev | Crystal melt-growth process wherein the melt surface is covered with an inert liquid |
| US3410679A (en) * | 1965-07-26 | 1968-11-12 | Tammet Internat | Method of making metal alloys, particularly ferrotitanium alloy |
| US4591382A (en) * | 1980-03-22 | 1986-05-27 | Elliott Guy R B | Process and apparatus for recovering and purifying uranium scrap |
| USH137H (en) | 1985-04-11 | 1986-10-07 | The United States Of America As Represented By The United States Department Of Energy | Process for reducing beta activity in uranium |
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