US3228748A - Process for the preparation of a uranium compound in powder form - Google Patents

Process for the preparation of a uranium compound in powder form Download PDF

Info

Publication number
US3228748A
US3228748A US161276A US16127661A US3228748A US 3228748 A US3228748 A US 3228748A US 161276 A US161276 A US 161276A US 16127661 A US16127661 A US 16127661A US 3228748 A US3228748 A US 3228748A
Authority
US
United States
Prior art keywords
uranium
metal
compound
refractory
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
Application number
US161276A
Inventor
Accary Andre
Dubuisson Jacques
Rousset Pierre
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Application granted granted Critical
Publication of US3228748A publication Critical patent/US3228748A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B21/00Nitrogen; Compounds thereof
    • C01B21/06Binary compounds of nitrogen with metals, with silicon, or with boron, or with carbon, i.e. nitrides; Compounds of nitrogen with more than one metal, silicon or boron
    • C01B21/0615Binary compounds of nitrogen with metals, with silicon, or with boron, or with carbon, i.e. nitrides; Compounds of nitrogen with more than one metal, silicon or boron with transition metals other than titanium, zirconium or hafnium
    • C01B21/063Binary compounds of nitrogen with metals, with silicon, or with boron, or with carbon, i.e. nitrides; Compounds of nitrogen with more than one metal, silicon or boron with transition metals other than titanium, zirconium or hafnium with one or more actinides, e.g. UN, PuN
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B32/00Carbon; Compounds thereof
    • C01B32/90Carbides
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B33/00Silicon; Compounds thereof
    • C01B33/06Metal silicides
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C32/00Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01PINDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00Particle morphology
    • C01P2004/30Particle morphology extending in three dimensions
    • C01P2004/32Spheres
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01PINDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00Particle morphology
    • C01P2004/60Particles characterised by their size
    • C01P2004/61Micrometer sized, i.e. from 1-100 micrometer
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01PINDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00Physical properties of inorganic compounds
    • C01P2006/80Compositional purity
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • This invention relates to processes for the preparation of powders and in particular, powders of refractory metal compounds, such as uranium carbide, uranium nitride and uranium silicide.
  • the object of the invention is to make such processes more economical than at present, particularly by dispensing with the grinding step generally necessitated in conventional methods.
  • a process for the preparation of a refractory metal compound in powder form comprises forming a metal-ceramic composition of the compound and of a metal, as hereinafter defined, treating the composition with at least one agent which acts upon the metal to cause disintegration of the composition and separating the desired compound in powder form.
  • the metal-ceramic composition is preferably formed by sintering the compound and the metal together.
  • metal as used in relation to the material associated with the refractory metal compound in the composition means a metal per se or such metal in alloyed form. It is preferably for the metal to be the same as that in the refractory compound.
  • the agent causes disintegration of the composition by chemical reaction with the metal.
  • the agent causes disintegration of the composition by dissolution of the metal.
  • the composition is subjected prior to disintegration to a grain-refining heat treatment.
  • Such powders are desired at present particularly in the nuclear energy field, especially in the preparation of dispersions in inert matrixes, such as graphite or metal, or in the preparation of agglomerates by compaction.
  • inert matrixes such as graphite or metal
  • agglomerates by compaction it is desirable to employ substantially spherical particles and rigorously controlled dimensions, for example a diameter of 100 microns. Since at present it is hardly possible to obtain them otherwise than by grinding uranium carbide or the like, previously formed by sintering or fusion, the grinding step represents a considerably energy consumption and does not readily lead to the desired particle size range.
  • a metal-ceramic composition that is a metallic ceramic containing the refractory metal compound to be obtained, for instance uranium carbide, and a metal alone or alloyed, namely in this instance uranium, i.e. the base metal of the compound, the disintegration taking place by reason of the chemical or physical action of an external agent (such as a reactant or solvent) and 3,228,748 Patented Jan. 11, 1966 undergoing transformation into powders, from which the desired metal compound is extracted, e.g. by physical or chemical separation.
  • an external agent such as a reactant or solvent
  • 3,228,748 Patented Jan. 11, 1966 undergoing transformation into powders, from which the desired metal compound is extracted, e.g. by physical or chemical separation.
  • the reaction in question gives a mixture in powder form containing both the residue from the reaction with or the dissolution of the metal and also the desired powder, which is separated out.
  • Such a process avoids any mechanical grinding treatment. It permits a good particle size to be obtained, particularly if the process includes, as is preferable, a heat treatment for modifying the grain structure prior to disintegration.
  • the proportions of the metal compound and of the metal in the initial metal-ceramic composition are desirably chosen in the appropriate manner. Proportions in the range of 60 to for the former and 40 to 5% for the latter are considered appropriate, though these amounts are not to be taken as limiting.
  • a cermet or metal-ceramic composition containing uranium monocarbide and uranium metal in the afore-mentioned proportions which correspond to a carbon content of the composition in the range of 3 to 4.4% by weight.
  • the carbon content of uranium monocarbide, UC is 4.8%, from which it will be seen that a proportion of 3 to 4.4% of carbon in the composition gives a major amount of UC and a minor amount of uncombined uranium metal.
  • uranium and pure carbon are used, for example, in the aforementioned proportions, and are subjected to sintering.
  • uranium oxide is used and is reduced by carbon.
  • This composition is subjected to a heat treatment for grain-refining or enlarging the particles of uranium carbide, regularising their shape and making their size uniform.
  • the heat treatment is effected, for instance, under a vacuum of about 10* to 10* mm. of mercury or in an inert atmosphere for a period of 1 to 8 hours at a temperature in the range of 1200 to 2200 C.
  • the disintegration step is effected, for instance by heating the metal-ceramic composition in the presence by hydrogen, under conditions conducive to the formation of uranium hydride.
  • This treatment is carried out in a suitable furnace, for example at a temperature in the range of 200 to 300 C. and under a hydrogen pressure of about 1 atmosphere.
  • uranium monocarbide and uranium hydride powders forms.
  • the mixture then has to be separated into its constituents.
  • the separation is effected for example by decantation in a liquid of appropriate density and viscosity or in any other manner, e.g. by centrifuging.
  • this separation may be effected directly on the uranium monocarbide and hydride derived from the afore-mentioned treatment or on a mixture of uranium carbide and uranium powder, after decomposition of the uranium hydride.
  • uranium nitride powders from a uranium nitride/ uranium metal-ceramic composition examples include uranium silicide (U Si powders from a metal-ceramic composition composed of the compound per se and the eutectic which it forms with uranium.
  • uranium nitride powders disintegration occurs, for instance, by the action on theuranium nitride/ uranium composition of normal hydrochloric acid, at a temperature of about 60 C., for example, thus producing uranium chloride which goes into solution.
  • the uranium nitride powder forms in this solution.
  • the reaction product is then subjected to filtration and the filtrate, namely the nitride powder, is Washed with water, dried with alcohol or acetone and then dried under vacuum.
  • uranium silicide action on the eutectic by one of the agents mentioned above for the carbide or the nitride or by some other agent causes decomposition into small particles, While the uranium silicide assumes the form of larger particles. It is thus appropriate to separate the two kinds of particles physically.
  • the grain-refining heat treatment should preferably be limited to temperatures in the range of 1000 to 1500 C.
  • a process for the production of powders of refractory uranium compounds selected from the group consisting of uranium carbide, uranium nitride and uranium silicide which comprises the steps of forming a mass of a metalceramic composition containing a major proportion of said compound and a minor proportion of uncombined uranium metal as the matrix metal of said mass, heating said composition at a temperature of from 1000 C. to 2200 C.
  • a process according to claim 1 in which a metal ceramic composition containing uranium nitride and uranium metal is contacted with hydrochloric acid which chemically reacts with the uranium metal to form uranium nitride powder in solution and the uranium nitride powder is separated by filtration.
  • the metalceramic composition initially contains 60 to 95% refractory uranium compound and to 5% uranium metal.
  • a process for the preparation of uranium silicide powder which comprises forming a metal-ceramic composition containing uranium silicide and its eutectic with uranium metal, treating the composition with an agent selected from the group consisting of hydrogen and hydrochloric acid to effect chemical reaction with the uranium metal and cause the formation of particles of uranium silicide and physically separating the uranium silicide particles from the other reaction products.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • Ceramic Engineering (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Carbon And Carbon Compounds (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Description

United States Patent 3,228,748 PROCESS FQR THE PREPARATION OF A URANI- UM COMPOUND IN POWDER FORM Andr Accary, Quai de la Gironde, Paris 19, Seine, France; Jacques Dubuisson, 2 Rue Wurtz, Paris 13, Seine, France; and Pierre Rousset, 30 Ave. Saint Laurent, Orsay, Seine-et-Oise, France No Drawing. Filed Dec. 21, 1961, Ser. No. 161,276
Claims priority, application France, Dec. 31, 1960,
15 Claims. (c1. 23-145 This invention relates to processes for the preparation of powders and in particular, powders of refractory metal compounds, such as uranium carbide, uranium nitride and uranium silicide.
The object of the invention is to make such processes more economical than at present, particularly by dispensing with the grinding step generally necessitated in conventional methods.
According to the invention, a process for the preparation of a refractory metal compound in powder form is provided, which comprises forming a metal-ceramic composition of the compound and of a metal, as hereinafter defined, treating the composition with at least one agent which acts upon the metal to cause disintegration of the composition and separating the desired compound in powder form.
The metal-ceramic composition is preferably formed by sintering the compound and the metal together.
The expression metal as used in relation to the material associated with the refractory metal compound in the composition means a metal per se or such metal in alloyed form. It is preferably for the metal to be the same as that in the refractory compound.
In one preferred embodiment of the invention, the agent causes disintegration of the composition by chemical reaction with the metal.
In another preferred embodiment of the invention, the agent causes disintegration of the composition by dissolution of the metal.
In accordance with a preferred feature of the invention, the composition is subjected prior to disintegration to a grain-refining heat treatment.
In carrying out the invention and, more particularly, those embodiments which are regarded at present as having preference, for example in connection with the preparation of powders of metal compounds such as uranium carbide (it being understood that the invention can be employed in obtaining other powders such as uranium nitride or uranium silicide), operation takes place as indicated below or in an analogous manner.
Such powders are desired at present particularly in the nuclear energy field, especially in the preparation of dispersions in inert matrixes, such as graphite or metal, or in the preparation of agglomerates by compaction. In these uses, it is desirable to employ substantially spherical particles and rigorously controlled dimensions, for example a diameter of 100 microns. Since at present it is hardly possible to obtain them otherwise than by grinding uranium carbide or the like, previously formed by sintering or fusion, the grinding step represents a considerably energy consumption and does not readily lead to the desired particle size range.
In carrying out the invention, use is made of the step of disintegration of a metal-ceramic composition, that is a metallic ceramic containing the refractory metal compound to be obtained, for instance uranium carbide, and a metal alone or alloyed, namely in this instance uranium, i.e. the base metal of the compound, the disintegration taking place by reason of the chemical or physical action of an external agent (such as a reactant or solvent) and 3,228,748 Patented Jan. 11, 1966 undergoing transformation into powders, from which the desired metal compound is extracted, e.g. by physical or chemical separation. In other words, the reaction in question gives a mixture in powder form containing both the residue from the reaction with or the dissolution of the metal and also the desired powder, which is separated out.
Such a process avoids any mechanical grinding treatment. It permits a good particle size to be obtained, particularly if the process includes, as is preferable, a heat treatment for modifying the grain structure prior to disintegration.
It is to be understood that the proportions of the metal compound and of the metal in the initial metal-ceramic composition are desirably chosen in the appropriate manner. Proportions in the range of 60 to for the former and 40 to 5% for the latter are considered appropriate, though these amounts are not to be taken as limiting.
Assuming that it is desired to prepare uranium carbide powder, operation takes place as follows:
There is first prepared, by one of the known methods, for example sintering a cermet or metal-ceramic composition containing uranium monocarbide and uranium metal in the afore-mentioned proportions, which correspond to a carbon content of the composition in the range of 3 to 4.4% by weight. The carbon content of uranium monocarbide, UC, is 4.8%, from which it will be seen that a proportion of 3 to 4.4% of carbon in the composition gives a major amount of UC and a minor amount of uncombined uranium metal.
In preparing the metal-ceramic composition, pure uranium and pure carbon are used, for example, in the aforementioned proportions, and are subjected to sintering. By an alternative known method, uranium oxide is used and is reduced by carbon.
This composition is subjected to a heat treatment for grain-refining or enlarging the particles of uranium carbide, regularising their shape and making their size uniform.
The heat treatment is effected, for instance, under a vacuum of about 10* to 10* mm. of mercury or in an inert atmosphere for a period of 1 to 8 hours at a temperature in the range of 1200 to 2200 C.
After the heat treatment, the disintegration step is effected, for instance by heating the metal-ceramic composition in the presence by hydrogen, under conditions conducive to the formation of uranium hydride.
This treatment is carried out in a suitable furnace, for example at a temperature in the range of 200 to 300 C. and under a hydrogen pressure of about 1 atmosphere.
Depending upon the conditions of treatment, a mixture of uranium monocarbide and uranium hydride powders forms. The mixture then has to be separated into its constituents.
The separation is effected for example by decantation in a liquid of appropriate density and viscosity or in any other manner, e.g. by centrifuging.
It is to be understood that this separation may be effected directly on the uranium monocarbide and hydride derived from the afore-mentioned treatment or on a mixture of uranium carbide and uranium powder, after decomposition of the uranium hydride.
In the latter case, decomposition of the hydride takes place, for example, by heating under vacuum, at a temperature of about 400 C., the vacuum being obtained by a high-throughput pump.
The above-described or an analogous process can be used for the preparation of many kinds of powder, such as uranium nitride powders from a uranium nitride/ uranium metal-ceramic composition, and uranium silicide (U Si powders from a metal-ceramic composition composed of the compound per se and the eutectic which it forms with uranium.
In the case of uranium nitride powders, disintegration occurs, for instance, by the action on theuranium nitride/ uranium composition of normal hydrochloric acid, at a temperature of about 60 C., for example, thus producing uranium chloride which goes into solution. The uranium nitride powder forms in this solution. The reaction product is then subjected to filtration and the filtrate, namely the nitride powder, is Washed with water, dried with alcohol or acetone and then dried under vacuum.
In the case of uranium silicide, action on the eutectic by one of the agents mentioned above for the carbide or the nitride or by some other agent causes decomposition into small particles, While the uranium silicide assumes the form of larger particles. It is thus appropriate to separate the two kinds of particles physically.
It may be mentioned that, in the case of the silicide, the grain-refining heat treatment should preferably be limited to temperatures in the range of 1000 to 1500 C.
Depending upon the particular procedure adopted, it is possible to prepare powders in a much more simple manner than at present, particularly because the grinding step, involving a high energy consumption, can be avoided.
As can be seen and as appears from the foregoing, the invention is not limited to the embodiments described nor to the ways of carrying out its various features especially envisaged above; it includes, on the contrary, all possible modifications.
What we claim is:
1. A process for the production of powders of refractory uranium compounds selected from the group consisting of uranium carbide, uranium nitride and uranium silicide, which comprises the steps of forming a mass of a metalceramic composition containing a major proportion of said compound and a minor proportion of uncombined uranium metal as the matrix metal of said mass, heating said composition at a temperature of from 1000 C. to 2200 C. for a time sufficient to regularize the shape and make uniform the size of the grains of said refractory uranium compound, forming particles of said compound by contacting said mass with at least one substance which chemically and selectively reacts with said uncombined matrix metal with disintegration of the mass into small particles of said refractory uranium compound and separating the particles of refractory uranium compound.
2. The process according to claim 1 in which said mass is disintegrated into substantially spherical particles of refractory uranium compound having a diameter of about 100 microns.
3. A process according to claim 1, in which the metalceramic composition is formed by sintering the uranium compound and the uranium metal together.
4. A process according to claim 1, in which the compound in powder form is separated mechanically from the other products produced by the action of the substance upon the metal.
5. A process according to claim 1, in which the compound in powder form is separated physically from the other products produced by the action of the substance upon the metal.
6. A process according to claim 1 in which a metal ceramic composition containing uranium nitride and uranium metal is contacted with hydrochloric acid which chemically reacts with the uranium metal to form uranium nitride powder in solution and the uranium nitride powder is separated by filtration.
7. A process according to claim 1 in which the substance which reacts chemically with the metal is selected from the group consisting of hydrogen and hydrochloric acid.
8. A process according to claim 1 in which the metalceramic composition initially contains 60 to 95% refractory uranium compound and to 5% uranium metal.
9. A process according to claim 6 in which the treatment with hydrochloric acid is effected at about 60 C. with normal hydrochloric acid.
10. A process for the preparation of uranium carbide powder, which comprises forming a metal-ceramic composition containing uranium monocarbide and uranium metal and having a carbon content of 3 to 4.4% by weight, treating the composition with hydrogen to form uranium hydride by chemical reaction with the uranium metal and separating the desired uranium carbide powder from the other products of the reaction by decantation in a liquid.
11. A process according to claim 10, in which the composition of. uranium monocarbide and uranium is subjected to a grain-refining heat treatment at a temperature of 1200 to 2200 C. for a period of 1 to 8 hours.
12. A process according to claim 10 in which the treatment with hydrogen is carried out at 200 to 300 C. under a hydrogen pressure of about one atmosphere.
13. A process according to claim 11 in which the grain refining treatment is carried out under vacuum of about 10- to 10- mm. of mercury.
14. A process for the preparation of uranium silicide powder, which comprises forming a metal-ceramic composition containing uranium silicide and its eutectic with uranium metal, treating the composition with an agent selected from the group consisting of hydrogen and hydrochloric acid to effect chemical reaction with the uranium metal and cause the formation of particles of uranium silicide and physically separating the uranium silicide particles from the other reaction products.
15. A process according to claim 14, in which the com position of uranium silicide and its eutectic with uranium metal is subjected to a grain-refining heat treatment at 1000 to 1500 C.
References Cited by the Examiner UNITED STATES PATENTS OTHER REFERENCES Dubuisson et al.: 2nd U.N International Conference on Peaceful Uses of Atomic Energy, vol. 6, pp. 551-560 (1958).
Katz et al.: The Chemistry of Uranium, page 240 (1951), McGraw-Hill Book Co., N.Y.C.
LEON D. ROSDOL, Primary Examiner.
CARL D. QUARFORTH, Examiner.
R. L. GRUDZIECKI, Assistant Examiner.

Claims (1)

1. A PROCESS FOR THE PRODUCTION OF POWDERS OF REFRACTORY URANIUM COMPOUNDS SELECTED FROM THE GROUP CONSISTING OF URANIUM CARBIDE, URANIUM NITRIDE AND URANIUM SILICIDE, WHICH COMPRISES THE STEPS OF FORMING A MASS OF A METALCERAMIC COMPOSITION CONTAINING A MAJOR PROPORTION OF SAID COMPOUND AND A MINOR PROPORTION OF UNCOMBINED URANIUM METAL AS THE MATRIX METAL OF SAID MASS, HEATING SAID COMPOSITION AT A TEMPERATURE OF FROM 1000*C. TO 2200*C. FOR A TIME SUFFICIENT TO REGULARIZE THE SHAPE AND MAKE UNIFORM THE SIZE OF THE GRAINS OF SAID REFRACTORY URANIUM COMPOUND, FORMING PARTICLES OF SAID COMPOUND BY CONTACTING SAID MASS WITH AT LEAST ONE SUBSTANCE WHICH CHEMICALLY AND SELECTIVELY REACTS WITH SAID UNCOMBINED MATRIX METAL WITH DISINTEGRATION OF THE MASS INTO SMALL PARTICLES OF SAID REFRACTORY URANIUM COMPOUND AND SEPARATING THE PARTICLES OF REFRACTORY URANIUM COMPOUND.
US161276A 1960-12-31 1961-12-21 Process for the preparation of a uranium compound in powder form Expired - Lifetime US3228748A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR848551A FR1284062A (en) 1960-12-31 1960-12-31 Improvements to processes for the preparation of powders, in particular based on uranium

Publications (1)

Publication Number Publication Date
US3228748A true US3228748A (en) 1966-01-11

Family

ID=8745893

Family Applications (1)

Application Number Title Priority Date Filing Date
US161276A Expired - Lifetime US3228748A (en) 1960-12-31 1961-12-21 Process for the preparation of a uranium compound in powder form

Country Status (8)

Country Link
US (1) US3228748A (en)
BE (1) BE611776A (en)
CH (1) CH407348A (en)
DE (1) DE1187232B (en)
FR (1) FR1284062A (en)
GB (1) GB1005393A (en)
LU (1) LU41026A1 (en)
NL (1) NL272727A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3860691A (en) * 1966-09-08 1975-01-14 Atomic Energy Commission Actinide mononitride microspheres and process
US3904736A (en) * 1966-06-01 1975-09-09 Grace W R & Co Preparing microspheres of actinide nitrides from carbon containing oxide sols

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10457558B2 (en) * 2017-06-22 2019-10-29 Westinghouse Electric Company Llc Method to produce uranium silicides

Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1488311A (en) * 1920-10-21 1924-03-25 Abrasive Company Method of purifying silicon-carbide crystals
US2158520A (en) * 1936-02-11 1939-05-16 Ig Farbenindustrie Ag Process for the production of hard carbides
US2485175A (en) * 1945-06-07 1949-10-18 Trapp George Joseph Method of recovering hard metal carbides from sintered masses
US2534676A (en) * 1945-02-16 1950-12-19 Amos S Newton Preparation of compounds of uranium and nonmetals
US2784054A (en) * 1944-12-05 1957-03-05 James H Carter Separation of uranium from other metals by hydriding and extraction with oxidizing reagents
US2913314A (en) * 1957-02-26 1959-11-17 Gen Electric Purification of tungsten carbide
US2926071A (en) * 1957-06-24 1960-02-23 Metal Hydrides Inc Preparation of titanium nitride of high purity
US2982619A (en) * 1957-04-12 1961-05-02 Roger A Long Metallic compounds for use in hightemperature applications
US3034889A (en) * 1944-09-29 1962-05-15 Frank H Spedding Decontamination of uranium

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2526805A (en) * 1944-08-12 1950-10-24 James H Carter Method of forming uranium carbon alloys
US2448479A (en) * 1944-09-06 1948-08-31 Atomic Energy Commission Uranium monocarbide and method of preparation

Patent Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1488311A (en) * 1920-10-21 1924-03-25 Abrasive Company Method of purifying silicon-carbide crystals
US2158520A (en) * 1936-02-11 1939-05-16 Ig Farbenindustrie Ag Process for the production of hard carbides
US3034889A (en) * 1944-09-29 1962-05-15 Frank H Spedding Decontamination of uranium
US2784054A (en) * 1944-12-05 1957-03-05 James H Carter Separation of uranium from other metals by hydriding and extraction with oxidizing reagents
US2534676A (en) * 1945-02-16 1950-12-19 Amos S Newton Preparation of compounds of uranium and nonmetals
US2485175A (en) * 1945-06-07 1949-10-18 Trapp George Joseph Method of recovering hard metal carbides from sintered masses
US2913314A (en) * 1957-02-26 1959-11-17 Gen Electric Purification of tungsten carbide
US2982619A (en) * 1957-04-12 1961-05-02 Roger A Long Metallic compounds for use in hightemperature applications
US2926071A (en) * 1957-06-24 1960-02-23 Metal Hydrides Inc Preparation of titanium nitride of high purity

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3904736A (en) * 1966-06-01 1975-09-09 Grace W R & Co Preparing microspheres of actinide nitrides from carbon containing oxide sols
US3860691A (en) * 1966-09-08 1975-01-14 Atomic Energy Commission Actinide mononitride microspheres and process

Also Published As

Publication number Publication date
NL272727A (en)
DE1187232B (en) 1965-02-18
LU41026A1 (en) 1962-03-01
BE611776A (en) 1962-04-16
GB1005393A (en) 1965-09-22
CH407348A (en) 1966-02-15
FR1284062A (en) 1962-02-09

Similar Documents

Publication Publication Date Title
Evans et al. Uranium nitrides
US3709667A (en) Dispersion strengthening of platinum group metals and alloys
CA2148406C (en) Process for producing very pure platinum materials, semifinished parts and foils dispersion-reinforced with y2o3
US3923933A (en) Process for preparing sintered uranium dioxide grains
US2834667A (en) Method of thermally reducing titanium oxide
US3096263A (en) Nuclear reactor fuel elements and method of preparation
US2884688A (en) Sintered ni-al-zr compositions
US3275564A (en) Process of fabrication of sintered compounds based on uranium and plutonium
US2905528A (en) Method for preparation of uo2 particles
US3228748A (en) Process for the preparation of a uranium compound in powder form
US3150975A (en) Method of making intermetallic compound-composition bodies
US3213032A (en) Process for sintering uranium nitride with a sintering aid depressant
US3114689A (en) Ceramic fuel for nuclear reactors
US3147543A (en) Dispersion hardened metal product
US3306957A (en) Production of nuclear fuel materials
US3046090A (en) Production of uranium monocarbide
US3141235A (en) Powdered tantalum articles
US3175903A (en) Process for forming porous tungsten
US3247297A (en) Process for the preparation of metallic materials by compression of a magnesium or magnesium alloy powder
US3264222A (en) Refractory material
US3236922A (en) Process for the preparation of uranium monocarbide-plutonium monocarbide fuel elements
US2823116A (en) Method of preparing sintered zirconium metal from its hydrides
US2952535A (en) Sintering metal oxides
US2905552A (en) Production of uranium metal by carbon reduction
US3172196A (en) Sintered intermetallic compoundcomposition bodies