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US2893928A - Preparation of plutonium - Google Patents

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US2893928A
US2893928A US23863A US2386348A US2893928A US 2893928 A US2893928 A US 2893928A US 23863 A US23863 A US 23863A US 2386348 A US2386348 A US 2386348A US 2893928 A US2893928 A US 2893928A
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plutonium
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    • AHUMAN NECESSITIES
    • A47FURNITURE; DOMESTIC ARTICLES OR APPLIANCES; COFFEE MILLS; SPICE MILLS; SUCTION CLEANERS IN GENERAL
    • A47KSANITARY EQUIPMENT NOT OTHERWISE PROVIDED FOR; TOILET ACCESSORIES
    • A47K3/00Baths; Douches; Appurtenances therefor
    • A47K3/16Devices for fastening baths to floors or walls; Adjustable bath feet ; Lining panels or attachments therefor
    • A47K3/162Collapsible stands or supports for baths
    • A47K3/164Collapsible stands or supports for baths for child or baby baths
    • CCHEMISTRY; METALLURGY
    • C25ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25CPROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C3/00Electrolytic production, recovery or refining of metals by electrolysis of melts
    • C25C3/34Electrolytic production, recovery or refining of metals by electrolysis of melts of metals not provided for in groups C25C3/02 - C25C3/32

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  • the primary object of this invention is, therefore, to provide a method for preparing pure plutonium.
  • an alkali metal halide or anv alkaline earth metal halide or mixtures of such halides are advantageously used in the fused bath as an auxiliary metal or metals because these alkali metals and alkaline earth metals are more electropositive than plutonium. It is preferable that the auxiliary metal halide or halides used in the bath have the same negative ion as the plutonium halide, and that Ithe bath have a low melting point. As an example. of
  • a low-melting point bath permits operation at a lower temperature with non-porous containers, vitreous *or metallic, in place of the graphite containers needed at.
  • Two tungsten rods 0.040 inch in diameter are connectedto the anode and cathode leads which are 0.38 inch apart and which extend through the top of a Pyrex container.
  • the Pyrex cell is evacuated and flushed with argon which has been dried and purified.
  • the rate of flow of the argon is adjusted to. a constant value to prevent the oxidation of the plutonium, which occurs rapidly, especially at higher temperatures.
  • 300 milligrams of the mixed salt and 59.4 milligrams of dry oxychloride-free plutonium trichloride are then introduced into the cell in'a drybox and the mixture is heated to 600 C. by means of the furnace which surrounds the container.
  • the anode and cathode are lowered into the bath and. a current of 0.20 ampere is maintained for 25 minutes at a potential of about 5 volts while the temperature is maintained at about 600 C.
  • the current and the furnace are turned oif, and the cell is cooled in the presence of argon. The argon is then turned off.
  • the plutonium Upon opening the cell, the plutonium is found to be in the form of a powder with some particles weighing from 3 to 4 milligrams. The recovery exceeds 50 percent and the plutonium assays percent plutonium.
  • the temperature of 600 C. used in this example is considerably less than that used in chemical conversion of plutonium above its melting point, and the dangers of toxic and radioactive fumes is therefore much less.
  • Example II presents the presently preferred embodiment of the method of the invention using one such metal container.
  • va current of 2.0 amperes is applied with a potential of about volts.
  • Complete electrolysis usually takes about 2.0 minutes.
  • the current and the furnace are turned oil.
  • the .cell is cooled in the presence of hydrogen and the hydrogen is turned off.
  • the salt is cleanly dislodged from the cell wall and is yellow-white in color.
  • the product is in the form of a well-collected single button of pure plutonium which has the melting point of pure plutonium, the density of pure plutonium, and assays .1000 percent pure plutonium. Microscopic study indicates that there is no evidence of alloying at theinterfaceof the plutonium and the molybdenum cell. The recovery of plutonium is usually greater than '75 percent.
  • all materials entering the .cell should. be thoroughly dry and the plutonium halide should be free of oxyhalides.
  • helium gas or the like may be used as the non-oxidizing atmosphere during .and after the electrolysis in place of or along with the.argon used in Example I or the hydrogen used in Example .II.'
  • the hydrogen has the feature of combining with the halogen released at theanode, thereby reducing its corrosiveness.
  • .it is possible to use other 'trihalides or tetrahalides .of plutonium .in place of the plutonium trichloride. .For example, :plutonium tetrachloride or plutonium .tetrafluoride may be used. It is also possible to use asauxiliary metals in the bath'other halides of the alkali or alkaline earth metals. For ex- .ample, a bath consisting of the-fluorides or mixtures of .chlorides and fluorides of;barium,rp.otassium, andsoditun .may be used.
  • Example II the initial concentration of the-plutonium trichloride was 1616 percent in Example I and 34.7:percentin Example II.
  • This concentration may, of course, be varied through a rather wide When working on :a small scale .a high initial concentration of plutonium causes .an excessive reduction .in the volume of the salt bath during electrolysis. .Spray and evaporationLlosses .are alsoincreased .with increase in concentration of .theplutonium. On the .other hand, a very low-initial concentration does :not yield as satisfactory deposits *ofplutoriium. Efiicient results may be obtained .from a-bath containing :from 5 '-to 75 percent .by
  • the preferred initial concentration is from 30 to 40 percent by weight. It has been found possible to continue electrolysis to the point where virtually no plutonium salt remains in the electrolyte.
  • the tungsten anode used in Example I may be used if all possibilities of carbon contamination are to be removed.
  • the cathode . may be of tungsten as in Example I, molybdenum as in Example II or other metals which are not appreciably soluble in the electrolyte, e.g., tantalum.
  • the temperature of the bath may also be varied within rather wide limits. It may be as low as 600 C., the temperature of the bath in Example I, or as high as 850 C. However, the range 750 C. to 850 C., is preferable, and a temperature of about 800 -C. has been found to give the best results.
  • the current may also be varied considerably. At a given current density, the recovery is reduced by an increase in temperature. This is to be expected because the cathode efliciency is reduced almost to zero by reaction of anode products with the metal. However, the recovery may be increased at constant temperature by increasing the current density. Current densities as high as amperes per square inch have been satisfactorily used.
  • the process can of course be carried out on a larger scale.
  • the cell construction can'be readily changed by methods well known to those skilled in the art to provide for continuous production. This process has high current efiiciency and low operating costs.
  • the process which comprises electrodepositing plutonium under non-oxidizing conditions from a fused bath consisting essentially of from 5 to 75 percent plutonium halide, said plutonium halide being thoroughly dry and free from oxyhalides, and at least one 'halide of ametal of the class consisting of alkali metals and alkaline earth metals, said fused bath being at a temperature between 600 C. and 850 C.
  • the process which comprises electrodepositing plutonium under non-oxidizing conditions from a fused bath .consisting essentially of from 5 to 75 percent plutonium halide, said plutonium halide being thoroughly dry and free from oxyhalides, and at least one alkali metal halide, said bath being at a temperature between 600 C. and 850 C.
  • the process which comprises velectrodepositingplutonium under :nonroxidizing conditions from a fused-bath consisting essentiallyof from 30 to 40 percent plutonium trichloride, said plutonium 'trichloride being thoroughly dry and free-from oxychlorides, and at least one chloride of a metal ofthe class consisting of alkali metals and .alkaline earth metals, ,said bath being at :a temperature .between'750 C. and 850 C.

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Description

July 7, 1959 M. KOLODNEY 2,893,928
PREPARATION OF PLUTONIUM Filed April 28, 1948 5 l6 /Fumace WITNESSES.
IN VEN TOR.
Morris Ko/adney PREPARATION OF PLUTONIUM Morris Kolodney, New York, N.Y., assignor to the United States of America as represented by the United States Atomic Energy Commission Application April 28, 1948, Serial No. 23,863
7 Claims. (Cl. 204-1.5)
This invention relates to methods for the electrodeposition of metals and more particularly to methods for the electrodeposition of plutonium.
It is desirable to prepare pure plutonium metal for many uses such as in neutron multiplying systems, neutronic reactors, experimental apparatus and the like. Pure plutonium may be produced by reducing plutonium compounds such as plutonium halides with an active metal.
This, however, has the disadvantage that such reactions must be carried out at a temperature above the melting point of plutonium, thus increasing the danger of radioactive and toxic fumes resulting from the greater volatility of the plutonium at the advanced temperatures. This method has the further disadvantage that small amounts of impurities are easily introduced.
The primary object of this invention is, therefore, to provide a method for preparing pure plutonium.
Another object of this invention is to provide a method I for eificiently preparing pure plutonium ata relatively low, temperature. I
Still further objects and advantages of this invention will appear-in the following description including the drawing hereby made a part of the specification wherein the figure is a "cross-sectional schematic of the apparatus of Example II.
The objects of this invention are achieved by the electrolysis of afused bath containing a plutonium halide. A number of different plutonium halides may be used in the fused bath as the source of the plutonium but the chlorides are more desirable than theother halides because they are relatively non-hygroscopic and have relatively low melting points. Of the plutonium chlorides, the trichloride is the preferred because it is readily made,
-it is less hygroscopic than the plutonium tetrachloride,
and the yield obtained when it is used for electrolysis is less aife'cted if some moisture is present.
An alkali metal halide or anv alkaline earth metal halide or mixtures of such halides are advantageously used in the fused bath as an auxiliary metal or metals because these alkali metals and alkaline earth metals are more electropositive than plutonium. It is preferable that the auxiliary metal halide or halides used in the bath have the same negative ion as the plutonium halide, and that Ithe bath have a low melting point. As an example. of
such a bath, a mixture of plutonium, barium, potassium,
and sodium chlorides'is very satisfactory because it has It is possible to prepare a rather low melting point. other baths with lower melting points, suchas a mixture of plutonium, lithium, potassium, and sodium chlorides. 4 A low-melting point bath permits operation at a lower temperature with non-porous containers, vitreous *or metallic, in place of the graphite containers needed at.
the higher temperature'ranges. This prevents losses due 5 to the relatively greater porosity of the graphite. It is,
of course, necessary that the containersdo not soften at 1 the temperature used and do not alloy with plutonium.
As an example of containers which 'havethe desired prop- 2,893,928 Patented July 7, 1959 "ice Example 1 Approximately ten grams each of reagent grade barium chloride, potassium chloride, and sodium chloride are thoroughly dried until all the moisture, including the water of crystallization, if any, is'rernoved. Each salt is then individually fused in platinum and cast in an inert metal vessel such as a platinum vessel. The salts are ground in a porcelain mortar. 2.4 grams of barium chloride, 1.55 grams of potassium chloride and 1.05 grams of sodium chloride, are thoroughly mixed, fused together, and reground. The mixture is kept in a desiccator and heated to 150 C. before use. Two tungsten rods 0.040 inch in diameter are connectedto the anode and cathode leads which are 0.38 inch apart and which extend through the top of a Pyrex container. The Pyrex cell is evacuated and flushed with argon which has been dried and purified. The rate of flow of the argon is adjusted to. a constant value to prevent the oxidation of the plutonium, which occurs rapidly, especially at higher temperatures. 300 milligrams of the mixed salt and 59.4 milligrams of dry oxychloride-free plutonium trichloride are then introduced into the cell in'a drybox and the mixture is heated to 600 C. by means of the furnace which surrounds the container. When the bath is molten the anode and cathode are lowered into the bath and. a current of 0.20 ampere is maintained for 25 minutes at a potential of about 5 volts while the temperature is maintained at about 600 C. The current and the furnace are turned oif, and the cell is cooled in the presence of argon. The argon is then turned off.
Upon opening the cell, the plutonium is found to be in the form of a powder with some particles weighing from 3 to 4 milligrams. The recovery exceeds 50 percent and the plutonium assays percent plutonium.
The temperature of 600 C. used in this example, is considerably less than that used in chemical conversion of plutonium above its melting point, and the dangers of toxic and radioactive fumes is therefore much less.
When it is desired not only to purify the plutonium, but also to obtain it in the form of a single massive piece of metal instead of inthe form of individual particles,
it is desirable to use a higher temperature'than the 600 C. used in Example I. The reduction at higher temperatures is not performed in Pyrex. Instead, a metal cell, such as one of those mentioned hereinbe'fore, is satisfactory. for such a use. a The operation at a higher temperature is illustrated in Example II, which presents the presently preferred embodiment of the method of the invention using one such metal container.
Example 7 II range.
see the figure, in the form of an inverted cone having an open top which rests on a graphite platform 11' and which is entirely enclosed in a V-ycor jacket 12. (The composition of Vycor is disclosed in Journal of Research of the National Bureau of Standards, vol. 26, 53.8 (1941)). A graphite rod 13, 025 inch in diameter extends into the top of the cell .and' is connected to an anode lead '14. The molybdenum cell is connected to a cathode lead 15. The system is evacuated and flushed with hydrogen through inlet 16, such hydrogen having been previously purified by passing over uranium chips .at 500 C. and been dried by passing through a train consisting of a .cold trap and a soda-lime and silica gel drying tower. The flow of hydrogen is continued during the processing, i.e., the hydrogen flows into the jacket through inlet 16 and out of the jacket between the bottom surface of jacket 12 and the furnace. The .furnace maybe of any type well known in the art. The hydrogen, like .the argon used in Example I, prevents the oxidation of the plutonium. The bath .is raised to a temperature .of about 600 C. The temperature is maintained by means of the furnace; the graphite rod is lowered into the bath and. the temperature of the bath is raised .to 800 C. while va current of 2.0 amperes is applied with a potential of about volts. Complete electrolysis usually takes about 2.0 minutes. The current and the furnace are turned oil. The .cell is cooled in the presence of hydrogen and the hydrogen is turned off. The salt is cleanly dislodged from the cell wall and is yellow-white in color. The product is in the form of a well-collected single button of pure plutonium which has the melting point of pure plutonium, the density of pure plutonium, and assays .1000 percent pure plutonium. Microscopic study indicates that there is no evidence of alloying at theinterfaceof the plutonium and the molybdenum cell. The recovery of plutonium is usually greater than '75 percent.
For maximum efliciency, all materials entering the .cell, particularly the plutonium halide, should. be thoroughly dry and the plutonium halide should be free of oxyhalides. When one of the plutonium chlorides is used, this .may be accomplished by placing .the plutonium compound in a stream of dry hydrogen chloride at a temperature below 80 C. until all moisture disappears,v increasing the temperature of the bath to about 280 C., .and maintaining it at this value for several hours.
-Many embodiments of the method of this invention are possible. For example, helium gas or the like may be used as the non-oxidizing atmosphere during .and after the electrolysis in place of or along with the.argon used in Example I or the hydrogen used in Example .II.' The hydrogen has the feature of combining with the halogen released at theanode, thereby reducing its corrosiveness.
As pointed out hereinbefore, .it is possible to use other 'trihalides or tetrahalides .of plutonium .in place of the plutonium trichloride. .For example, :plutonium tetrachloride or plutonium .tetrafluoride may be used. It is also possible to use asauxiliary metals in the bath'other halides of the alkali or alkaline earth metals. For ex- .ample, a bath consisting of the-fluorides or mixtures of .chlorides and fluorides of;barium,rp.otassium, andsoditun .may be used.
It may be noted that in'theexamples the initial concentration of the-plutonium trichloridewas 1616 percent in Example I and 34.7:percentin Example II. This concentration may, of course, be varied through a rather wide When working on :a small scale .a high initial concentration of plutonium causes .an excessive reduction .in the volume of the salt bath during electrolysis. .Spray and evaporationLlosses .are alsoincreased .with increase in concentration of .theplutonium. On the .other hand, a very low-initial concentration does :not yield as satisfactory deposits *ofplutoriium. Efiicient results may be obtained .from a-bath containing :from 5 '-to 75 percent .by
weight plutonium, .but tthe preferred initial concentration is from 30 to 40 percent by weight. It has been found possible to continue electrolysis to the point where virtually no plutonium salt remains in the electrolyte.
In like manner, although the graphite used as anode in Example II is not appreciably affected by the bath, the tungsten anode used in Example I may be used if all possibilities of carbon contamination are to be removed. The cathode .may be of tungsten as in Example I, molybdenum as in Example II or other metals which are not appreciably soluble in the electrolyte, e.g., tantalum.
The temperature of the bath may also be varied within rather wide limits. It may be as low as 600 C., the temperature of the bath in Example I, or as high as 850 C. However, the range 750 C. to 850 C., is preferable, and a temperature of about 800 -C. has been found to give the best results.
The current may also be varied considerably. At a given current density, the recovery is reduced by an increase in temperature. This is to be expected because the cathode efliciency is reduced almost to zero by reaction of anode products with the metal. However, the recovery may be increased at constant temperature by increasing the current density. Current densities as high as amperes per square inch have been satisfactorily used.
The process can of course be carried out on a larger scale. The cell construction can'be readily changed by methods well known to those skilled in the art to provide for continuous production. This process has high current efiiciency and low operating costs.
Because'there are so many embodiments of'the method of this invention, it is to be understood that this invention is not to be limited except as indicated in the .appended claims.
What is claimed is:
1. The process which comprises electrodepositing plutonium under non-oxidizing conditions from a fused bath consisting essentially of from 5 to 75 percent plutonium halide, said plutonium halide being thoroughly dry and free from oxyhalides, and at least one 'halide of ametal of the class consisting of alkali metals and alkaline earth metals, said fused bath being at a temperature between 600 C. and 850 C.
2. The process which comprises electrodepositing plutonium under non-oxidizing conditions from a fused bath .consisting essentially of from 5 to 75 percent plutonium halide, said plutonium halide being thoroughly dry and free from oxyhalides, and at least one alkali metal halide, said bath being at a temperature between 600 C. and 850 C.
3. The process which comprises electrodepositing:plutoniumxunder non-oxidizingconditionsfrom a fused bath consisting essentially of from 5 to75 percent plutonium halide, said plutonium halide being thoroughly dry and free fromoxyhalides, and at least one alkaline'earth metal halide, said bath'being at a temperature between 600 and 850 C.
4. The process which comprises electrodepositing plutonium under non-oxidizing conditions/from a fused bath consisting essentially of from ,5 .to .75 percent plutonium trichloride, said plutonium trichloride .being thoroughly dry and 'free from oxychlorides, and at least one alkali metal chloride and at -*least one alkaline earth metal chloride, said bath being-at a temperature between600 C. and 850 C.
.5. The process which comprises velectrodepositingplutonium under :nonroxidizing conditions from a fused-bath consisting essentiallyof from 30 to 40 percent plutonium trichloride, said plutonium 'trichloride being thoroughly dry and free-from oxychlorides, and at least one chloride of a metal ofthe class consisting of alkali metals and .alkaline earth metals, ,said bath being at :a temperature .between'750 C. and 850 C.
6. The process which comprises electrodepositing plutonium under non-oxidizing conditions from a fused bath containing from 5 to 75 percent plutonium trichloride, said plutonium trichloride being thoroughly dry and free from oxychlorides, and the balance of barium chloride, potassium chloride and sodium chloride, said bath being at a temperature between 600 C. and 850 C.
7. The process which comprises electrodepositing plutonium under non-oxidizing conditions from a fused bath containing from 30 to 40 percent plutonium trichloride, said plutonium trichloride being thoroughly dry and free from oXychlorides, and the balance of a mixture of 48 percent barium chloride, 31 percent potassium chloride and 21 percent sodium chloride, said bath being at a temperature of about 800 C.
References Cited in the file of this patent UNITED STATES PATENTS 1,821,176 Driggs et al Sept. 1, 1931 1,842,254 Driggs Jan. 19, 1932 1,861,625 Dn'ggs et al. June 7, 1932 2,519,792 Rosen Aug. 22, 1950 2,690,421 Lilliendahl et a1. Sept. 28, 1954 OTHER REFERENCES Ind. Eng. Chem., vol. 22, No. 5, pp. 5165l9, May 1930.
Chem. Eng. News, vol. 23, 2192 (1945).
The T ransuranium Elements, edited by G. T. Seaborg, J. J. Katz, and W. M. Manning, Pt. 1, 1st ed. (1949), McGraw-Hill Book Co., N.Y., page 160.

Claims (1)

1. THE PROCESS WHICH COMPRISES ELECTRODEPOSITING PLUTONIUM UNDER NON-OXIDIZING CONDITIONS FROM A FUSED BATH CONSISTING ESSENTIALLY OF FROM 5 TO 75 PERCENT PLUTONIUM HALIDE, SAID PLUTONIUM HALIDE BEING THOROUGHLY DRY AND FREE FROM OXYHALIDES, AND AT LEAST ONE HALIDE OF A METAL OF THE CLASS CONSISTING OF ALKALI METALS AND ALKALINE EARTH METALS, SAID FUSED BATH BEING AT A TEMPERATURE BETWEEN 600* C. AND 850* C.
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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2923670A (en) * 1958-04-04 1960-02-02 Carl W Bjorklund Method and means for electrolytic purification of plutonium
US3011865A (en) * 1960-08-22 1961-12-05 Glen E Benedict Separation of uranium and plutonium oxides
US3282806A (en) * 1965-08-04 1966-11-01 Jack L Long Electrorefining of plutonium
US4995948A (en) * 1989-07-24 1991-02-26 The United States Of America As Represented By The United States Department Of Energy Apparatus and process for the electrolytic reduction of uranium and plutonium oxides

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1821176A (en) * 1928-10-01 1931-09-01 Westinghouse Lamp Co Method of preparing rare refractory metals
US1842254A (en) * 1928-05-11 1932-01-19 Westinghouse Lamp Co Preparation of rare metals by electrolytic decomposition of their fused double halogen compounds
US1861625A (en) * 1929-03-30 1932-06-07 Westinghouse Lamp Co Method of producing rare metals by electrolysis
US2519792A (en) * 1942-04-10 1950-08-22 Rosen Raphael Electrolytic production of metallic uranium
US2690421A (en) * 1943-03-06 1954-09-28 William C Lilliendahl Electrolytic production of uranium powder

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1842254A (en) * 1928-05-11 1932-01-19 Westinghouse Lamp Co Preparation of rare metals by electrolytic decomposition of their fused double halogen compounds
US1821176A (en) * 1928-10-01 1931-09-01 Westinghouse Lamp Co Method of preparing rare refractory metals
US1861625A (en) * 1929-03-30 1932-06-07 Westinghouse Lamp Co Method of producing rare metals by electrolysis
US2519792A (en) * 1942-04-10 1950-08-22 Rosen Raphael Electrolytic production of metallic uranium
US2690421A (en) * 1943-03-06 1954-09-28 William C Lilliendahl Electrolytic production of uranium powder

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2923670A (en) * 1958-04-04 1960-02-02 Carl W Bjorklund Method and means for electrolytic purification of plutonium
US3011865A (en) * 1960-08-22 1961-12-05 Glen E Benedict Separation of uranium and plutonium oxides
US3282806A (en) * 1965-08-04 1966-11-01 Jack L Long Electrorefining of plutonium
US4995948A (en) * 1989-07-24 1991-02-26 The United States Of America As Represented By The United States Department Of Energy Apparatus and process for the electrolytic reduction of uranium and plutonium oxides

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