US2849308A - Flux composition and method for treating uranium-containing metal - Google Patents
Flux composition and method for treating uranium-containing metal Download PDFInfo
- Publication number
- US2849308A US2849308A US632598A US63259845A US2849308A US 2849308 A US2849308 A US 2849308A US 632598 A US632598 A US 632598A US 63259845 A US63259845 A US 63259845A US 2849308 A US2849308 A US 2849308A
- Authority
- US
- United States
- Prior art keywords
- percent
- uranium
- flux
- weight
- alloys
- 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 18
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims description 18
- 229910052751 metal Inorganic materials 0.000 title claims description 13
- 239000002184 metal Substances 0.000 title claims description 13
- 239000000203 mixture Substances 0.000 title claims description 7
- 238000000034 method Methods 0.000 title claims description 4
- 229910045601 alloy Inorganic materials 0.000 claims description 10
- 239000000956 alloy Substances 0.000 claims description 10
- 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
- MZFRHHGRNOIMLW-UHFFFAOYSA-J uranium(4+);tetrafluoride Chemical compound F[U](F)(F)F MZFRHHGRNOIMLW-UHFFFAOYSA-J 0.000 claims description 8
- UXVMQQNJUSDDNG-UHFFFAOYSA-L Calcium chloride Chemical compound [Cl-].[Cl-].[Ca+2] UXVMQQNJUSDDNG-UHFFFAOYSA-L 0.000 claims description 7
- 229910001628 calcium chloride Inorganic materials 0.000 claims description 7
- 239000001110 calcium chloride Substances 0.000 claims description 7
- 238000002844 melting Methods 0.000 claims description 7
- 230000008018 melting Effects 0.000 claims description 6
- 150000002739 metals Chemical class 0.000 claims description 5
- 230000001681 protective effect Effects 0.000 description 4
- 229910000711 U alloy Inorganic materials 0.000 description 3
- 230000005484 gravity Effects 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
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 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
- 239000004615 ingredient Substances 0.000 description 1
- 239000010410 layer 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
- 239000011241 protective layer Substances 0.000 description 1
- 230000000284 resting effect Effects 0.000 description 1
- -1 uranium Chemical class 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
-
- 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
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, calcium chloride and uranium tetrafluoride. I have discovered that proportions of the various ingredients 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 50 percent to 70 percent by weight calcium fluoride, 20 percent to 40 percent by weight calcium chloride, and 5 percent to 15 percent by weight uranium tetrafluoride.
- uranium-lead alloys approximately percent by weight of calcium fluoride 30 percent by weight of calcium chloride and 10 percent 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 suflicient 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 metals wherein uranium predominates comprising about 50 percent to percent by weight of calcium fluoride, about 20 percent to 40 percent by weight of calcuim chloride and about 5 percent to 15 percent by weight of uranium tetrafluoride.
- a flux composition for use with molten uranium and alloys thereof wherein uranium predominates comprising about 60 percent by weight of calcium fluoride, about 30 percent by weight of calcium chloride and about 10 percent by weight of uranium tetrafluoride.
- a flux comprising about 50 to 70 percent by weight of calcium fluoride, about 20 to 40 percent by weight of calcium chloride and about 5 to 15 percent by weight of uranium tetrafluoride.
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- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Physics & Mathematics (AREA)
- Manufacturing & Machinery (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Materials Engineering (AREA)
- Life Sciences & Earth Sciences (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- Dispersion Chemistry (AREA)
- Environmental & Geological Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Electric Connection Of Electric Components To Printed Circuits (AREA)
Description
United Stats FLUX COMPOSITION AND MET H 313 FOR TREAT- ING URANIUM-CONTAINING METAL Frank Foote, Chicago, 111., assignor to the United States of America as represented by the United States Atomic Energy Commission No Drawing. Application December 3, 1945 Serial No. 632,598
3 Claims. (Cl. 75--84.1)
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 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 to cover the same with a substantially inert protective layer 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 protective flux is particularly diflicult when highly reactive metals, such as uranium, are to be protected.
I have discovered a new flux which is particularly adapted for use in the melting of uranium and its alloys. especially those alloys in which uranium is the predominant component.
The flux which I have found suitable to employ for the purposes above-mentioned is compounded in such manner that is 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 1000-1100 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, calcium chloride and uranium tetrafluoride. I have discovered that proportions of the various ingredients 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 50 percent to 70 percent by weight calcium fluoride, 20 percent to 40 percent by weight calcium chloride, and 5 percent to 15 percent by weight uranium tetrafluoride.
As a specific example of the preparation of a suitable flux and its use in preparing uranium-lead alloys, approximately percent by weight of calcium fluoride 30 percent by weight of calcium chloride and 10 percent 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 suflicient 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 metals wherein uranium predominates, said flux comprising about 50 percent to percent by weight of calcium fluoride, about 20 percent to 40 percent by weight of calcuim chloride and about 5 percent to 15 percent by weight of uranium tetrafluoride.
2. A flux composition for use with molten uranium and alloys thereof wherein uranium predominates, said flux comprising about 60 percent by weight of calcium fluoride, about 30 percent by weight of calcium chloride and about 10 percent by weight of uranium tetrafluoride.
3. In a method of melting uranium and uranium base alloys the step of adding a flux comprising about 50 to 70 percent by weight of calcium fluoride, about 20 to 40 percent by weight of calcium chloride and about 5 to 15 percent by weight of uranium tetrafluoride.
References Cited in the file of this patent UNITED STATES PATENTS 1,673,043 Fischer June 12, 1928 2,040,283 Swartz May 12, 1936 2,051,963 Monroe et al Aug. 25, 1936 2,327,065 Reimers Aug. 17, 1943
Claims (2)
1. A FLUX COMPOSITION FOR USE WITH METALS WHEREIN URANIUM PREDOMINATES, SAID FLUX COMPRISISNG ABOUT 50 PERCENT TO 70 PERCENT BY WEIGHT OF CALCIUM FLUORIDE, ABOUT 20 PERCENT TO 40 PERCENT BY WEIGHT OF CALCIUM CHLORIDE AND ABOUT 5 PERCENT TO 15 PERCENT BY WEIGHT OF URANIUM TETRAFLUORIDE.
3. IN A METHOD OF MELTING URANIUM AND URANIUM BASE ALLOYS THE STEP OF ADDING A FLUX COMPRISING ABOUT 50 TO 70 PERCENT BY WEIGHT OF CALCIUM FLUORIDE, ABOUT 20 TO 40 PERCENT BY WEIGHT OF CALCIUM CHLORIDE AND ABOUT 5 TO 15 PERCENT BY WEIGHT OF URANIUM TETRAFLUORIDE.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US632598A US2849308A (en) | 1945-12-03 | 1945-12-03 | Flux composition and method for treating uranium-containing metal |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US632598A US2849308A (en) | 1945-12-03 | 1945-12-03 | Flux composition and method for treating uranium-containing metal |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US2849308A true US2849308A (en) | 1958-08-26 |
Family
ID=24536170
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US632598A Expired - Lifetime US2849308A (en) | 1945-12-03 | 1945-12-03 | Flux composition and method for treating uranium-containing metal |
Country Status (1)
| Country | Link |
|---|---|
| US (1) | US2849308A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3109731A (en) * | 1961-12-19 | 1963-11-05 | James B Knighton | Production of actinide metal |
| US3849211A (en) * | 1973-06-13 | 1974-11-19 | S Gurevich | Flux for welding refractory and non-ferrous metals |
| US4591382A (en) * | 1980-03-22 | 1986-05-27 | Elliott Guy R B | Process and apparatus for recovering and purifying uranium scrap |
| 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 (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US1673043A (en) * | 1925-09-10 | 1928-06-12 | Siemens Ag | Method for the producing of technical pure beryllium respectively for freeing metallic beryllium from impurities |
| 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 US632598A patent/US2849308A/en not_active Expired - Lifetime
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US1673043A (en) * | 1925-09-10 | 1928-06-12 | Siemens Ag | Method for the producing of technical pure beryllium respectively for freeing metallic beryllium from impurities |
| 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 (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3109731A (en) * | 1961-12-19 | 1963-11-05 | James B Knighton | Production of actinide metal |
| US3849211A (en) * | 1973-06-13 | 1974-11-19 | S Gurevich | Flux for welding refractory and non-ferrous metals |
| US4591382A (en) * | 1980-03-22 | 1986-05-27 | Elliott Guy R B | Process and apparatus for recovering and purifying uranium scrap |
| 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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