US2849307A - Method and flux composition for treating uranium - Google Patents
Method and flux composition for treating uranium Download PDFInfo
- Publication number
- US2849307A US2849307A US632599A US63259945A US2849307A US 2849307 A US2849307 A US 2849307A US 632599 A US632599 A US 632599A US 63259945 A US63259945 A US 63259945A US 2849307 A US2849307 A US 2849307A
- Authority
- US
- United States
- Prior art keywords
- uranium
- flux
- weight
- alloys
- flux composition
- 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
- 230000004907 flux Effects 0.000 title claims description 26
- 229910052770 Uranium Inorganic materials 0.000 title claims description 20
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims description 20
- 239000000203 mixture Substances 0.000 title claims description 7
- 238000000034 method Methods 0.000 title claims description 5
- 229910045601 alloy Inorganic materials 0.000 claims description 11
- 239000000956 alloy Substances 0.000 claims description 11
- WUKWITHWXAAZEY-UHFFFAOYSA-L calcium difluoride Chemical compound [F-].[F-].[Ca+2] WUKWITHWXAAZEY-UHFFFAOYSA-L 0.000 claims description 8
- 229910001634 calcium fluoride Inorganic materials 0.000 claims description 8
- ORUIBWPALBXDOA-UHFFFAOYSA-L magnesium fluoride Chemical compound [F-].[F-].[Mg+2] ORUIBWPALBXDOA-UHFFFAOYSA-L 0.000 claims description 8
- 229910001635 magnesium fluoride Inorganic materials 0.000 claims description 8
- 238000002844 melting Methods 0.000 claims description 7
- 230000008018 melting Effects 0.000 claims description 7
- MZFRHHGRNOIMLW-UHFFFAOYSA-J uranium(4+);tetrafluoride Chemical compound F[U](F)(F)F MZFRHHGRNOIMLW-UHFFFAOYSA-J 0.000 claims description 6
- 229910052751 metal Inorganic materials 0.000 description 9
- 239000002184 metal Substances 0.000 description 9
- 229910000711 U alloy Inorganic materials 0.000 description 4
- 230000001681 protective effect Effects 0.000 description 4
- 230000005484 gravity Effects 0.000 description 3
- 150000002739 metals Chemical class 0.000 description 3
- 239000012530 fluid Substances 0.000 description 2
- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 238000010301 surface-oxidation reaction Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 229910000978 Pb alloy Inorganic materials 0.000 description 1
- BILXWNHAXOTCQI-UHFFFAOYSA-N [Pb].[U] Chemical compound [Pb].[U] BILXWNHAXOTCQI-UHFFFAOYSA-N 0.000 description 1
- 238000005275 alloying Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 230000000284 resting effect Effects 0.000 description 1
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
- C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
-
- 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
- C22B9/00—General processes of refining or remelting of metals; Apparatus for electroslag or arc remelting of metals
- C22B9/10—General processes of refining or remelting of metals; Apparatus for electroslag or arc remelting of metals with refining or fluxing agents; Use of materials therefor, e.g. slagging or scorifying agents
Definitions
- the present invention relates to protective fluxes and is particularly concerned with providing protective fluxes for the melting of uranium and alloys of uranium.
- a flux having such properties can be prepared by admixing in suitable proportions calcium fluoride, magnesium fluoride and uranium tetrafluoride. I have discovered that proportions of the various ingredicuts in this flux may be varied somewhat without substantially changing the desirable characteristics of my new and novel flux. I have found that the composition of a suitable flux, calculated on an anhydrous basis, may vary from about 35% to by weight calcium fluoride, 35% to 55% by weight magnesium fluoride, and 5% to 15 by weight uranium tetrafiuoride.
- uranium-lead alloys approximately 46% by weight of calcium fluoride, 46% by weight of magnesium fluoride, and 8% by Weight of uranium tetrafluoride were thoroughly mixed together. The flux was then placed in a graphite crucible and melted; thereafter uranium metal was charged into the crucible and melted, and then lead was added in an amount suificient to form the desired alloy. No substantial oxidation of the uranium occurred since the protective flux formed a molten layer resting upon and protecting the molten uranium.
- a flux composition for use with molten uranium and alloys that have a predominant content of uranium comprising about 35% to 55% by weight of calcium fluoride, about 35% to 55% by weight of magnesium fluoride, and about 5% to 15% by weight of uranium tetrafluoride.
- a flux composition for use with molten uranium and alloys thereof that have a predominant content of uranium comprisingabout 46% by weight of calcium fluoride, about. 46% by weight of magnesium fluoride, and about 8% by weight of uranium tetrafluoride.
- a flux comprising about 35 to 55% by weight of calcium fluoride, about 35 to 55% of magnesium fluoride, and about 5 to 15% by weight of uranium tetrafluoride.
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- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Environmental & Geological Engineering (AREA)
- Geology (AREA)
- Electric Connection Of Electric Components To Printed Circuits (AREA)
Description
United States Patet METHOD AND FLUX COMPOSITION FOR TREATING URANIUM Frank Foote, Chicago, Ill., assignor to the United States of America as represented by the United States Atomic Energy Commission No Drawing. Application December 3, 1345 Serial No. 632,599
3 Claims. (Cl. 7584) The present invention relates to protective fluxes and is particularly concerned with providing protective fluxes for the melting of uranium and alloys of uranium.
In the past, several fluxes or mixtures of flux materials have been used for the protection of molten metals in order to prevent surface oxidation or to hinder the volatilization of low melting point metals during alloying processes. Certain fundamental requisites must be met by this type of flux. For example, it must have a melting point considerably below that of the metal and its alloys. At the same time the flux must have the proper specific gravity and surface tension in order to float on the metal or alloy when in molten condition and at the same time cover the same with an inert protective film, in order to prevent undue oxidation thereof, and also to prevent volatilization of the metal and its alloys. In addition there must, of course, be no chemical reaction between the flux and the metal or its alloys. Very few fluxes meet all of the foregoing requirements, the majority being ruled out because they react with the metal or do not have the required combination of specific gravity and surface tension to prevent surface oxidation or volatilization. The problem of securing a suitable flux is particularly diflicult when highly reactive metals, such as uranium and alloys in which uranium is a predominant component, are to be protected.
I have discovered a new flux which is particularly adapted for use in melting uranium and uranium alloys.
The flux which I have found suitable to employ for the purposes above-mentioned is compounded in such manner that it possesses the following physical properties:
(1) It is fluid at temperatures below the melting point of uranium and commercial uranium alloys, i. e., it melts at approximately 9001000 C.; and
(2) It has a lower specific gravity when fluid than molten uranium or commercial uranium alloys.
I have found that a flux having such properties can be prepared by admixing in suitable proportions calcium fluoride, magnesium fluoride and uranium tetrafluoride. I have discovered that proportions of the various ingredicuts in this flux may be varied somewhat without substantially changing the desirable characteristics of my new and novel flux. I have found that the composition of a suitable flux, calculated on an anhydrous basis, may vary from about 35% to by weight calcium fluoride, 35% to 55% by weight magnesium fluoride, and 5% to 15 by weight uranium tetrafiuoride.
As a specific example of the preparation of a suitable flux and its use in preparing uranium-lead alloys, approximately 46% by weight of calcium fluoride, 46% by weight of magnesium fluoride, and 8% by Weight of uranium tetrafluoride were thoroughly mixed together. The flux was then placed in a graphite crucible and melted; thereafter uranium metal was charged into the crucible and melted, and then lead was added in an amount suificient to form the desired alloy. No substantial oxidation of the uranium occurred since the protective flux formed a molten layer resting upon and protecting the molten uranium.
It will be apparent to those skilled in the art to which this invention pertains that various modifications may be made without departing from the principles of the invention as disclosed herein, and thus it is not intended that the invention should be limited other than by the scope of the appended claims.
What is claimed is:
1. A flux composition for use with molten uranium and alloys that have a predominant content of uranium, said flux comprising about 35% to 55% by weight of calcium fluoride, about 35% to 55% by weight of magnesium fluoride, and about 5% to 15% by weight of uranium tetrafluoride.
2. A flux composition for use with molten uranium and alloys thereof that have a predominant content of uranium, said flux comprisingabout 46% by weight of calcium fluoride, about. 46% by weight of magnesium fluoride, and about 8% by weight of uranium tetrafluoride.
3. In a method of melting uranium and uranium-base alloys the step of adding a flux comprising about 35 to 55% by weight of calcium fluoride, about 35 to 55% of magnesium fluoride, and about 5 to 15% by weight of uranium tetrafluoride.
References Cited in the file of this patent UNITED STATES PATENTS 2,040,283 Swartz May 12, 1936 2,051,963 Monroe et al. Aug. 25, 1936 2,327,065 Reimers Aug. 17, 1943 OTHER REFERENCES International Critical Tables, vol. 4, page 62, published by McGraw-Hill Book Co., New York, N. Y.
Claims (2)
1. A FLUX COMPOSITION FOR USE WITH MOLTEN URANIUM AND ALLOYS THAT HAVE A PREDOMINANT CONTENT OF URANIUM, SAID FLUX COMPRISING ABOUT 35% TO 55% BY WEIGHT OF CALCIUM FLUORIDE, ABOUT 35% TO 55% BY WEIGHT OF MAGNESIUM FLUORIDE, AND ABOUT 5% TO 15% BY WEIGHT OF URANIUM TETRAFLUORIDE.
3. IN A METHOD OF MELTING URANIUM AND URANIUM-BASE ALLOYS THE STEP OF ADDING A FLUX COMPRISING ABOUT 35 TO 55% BY WEIGHT OF CALCIUM FLUORIDE, ABOUT 35% TO 55% OF MAGNESIUM FLUORIDE, AND ABOUT 5 TO 15% BY WEIGHT OF URIANIUM TETRAFLUORIDE.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US632599A US2849307A (en) | 1945-12-03 | 1945-12-03 | Method and flux composition for treating uranium |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US632599A US2849307A (en) | 1945-12-03 | 1945-12-03 | Method and flux composition for treating uranium |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US2849307A true US2849307A (en) | 1958-08-26 |
Family
ID=24536177
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US632599A Expired - Lifetime US2849307A (en) | 1945-12-03 | 1945-12-03 | Method and flux composition for treating uranium |
Country Status (1)
| Country | Link |
|---|---|
| US (1) | US2849307A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0198967A1 (en) * | 1985-04-16 | 1986-10-29 | Guy Rupert Betts Elliott | Process and apparatus for separating actinide or lanthanide metals or their alloys from salts |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2040283A (en) * | 1934-04-14 | 1936-05-12 | American Smelting Refining | Flux for cadmium and its alloys and method for regenerating same |
| US2051963A (en) * | 1932-05-28 | 1936-08-25 | Beryllium Corp | Method for treating beryllium and its alloys |
| US2327065A (en) * | 1941-08-30 | 1943-08-17 | Dow Chemical Co | Welding flux for magnesium base alloys |
-
1945
- 1945-12-03 US US632599A patent/US2849307A/en not_active Expired - Lifetime
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2051963A (en) * | 1932-05-28 | 1936-08-25 | Beryllium Corp | Method for treating beryllium and its alloys |
| US2040283A (en) * | 1934-04-14 | 1936-05-12 | American Smelting Refining | Flux for cadmium and its alloys and method for regenerating same |
| US2327065A (en) * | 1941-08-30 | 1943-08-17 | Dow Chemical Co | Welding flux for magnesium base alloys |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0198967A1 (en) * | 1985-04-16 | 1986-10-29 | Guy Rupert Betts Elliott | Process and apparatus for separating actinide or lanthanide metals or their alloys from salts |
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