US3275564A - Process of fabrication of sintered compounds based on uranium and plutonium - Google Patents

Process of fabrication of sintered compounds based on uranium and plutonium Download PDF

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US3275564A
US3275564A US286958A US28695863A US3275564A US 3275564 A US3275564 A US 3275564A US 286958 A US286958 A US 286958A US 28695863 A US28695863 A US 28695863A US 3275564 A US3275564 A US 3275564A
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plutonium
uranium
alloy
powder
sintered
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Pascard Roger
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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    • 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
    • G21C3/62—Ceramic fuel
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B22—CASTING; POWDER METALLURGY
    • B22F—WORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F9/00—Making metallic powder or suspensions thereof
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B21/00—Nitrogen; Compounds thereof
    • C01B21/06—Binary 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
    • C01B21/0602—Binary 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 two or more other elements chosen from metals, silicon or boron
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B32/00—Carbon; Compounds thereof
    • C01B32/90—Carbides
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C1/00—Making non-ferrous alloys
    • C22C1/04—Making non-ferrous alloys by powder metallurgy
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C32/00—Non-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
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C32/00—Non-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
    • C22C32/0047—Non-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 with carbides, nitrides, borides or silicides as the main non-metallic constituents
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C43/00—Alloys containing radioactive materials
    • 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
    • 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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/60—Particles characterised by their size
    • C01P2004/61—Micrometer sized, i.e. from 1-100 micrometer
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/80—Particles consisting of a mixture of two or more inorganic phases
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/80—Compositional purity
    • 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

  • uranium-plutonium alloys having plutonium contents from 15 to 80% are very fragile, because of the presence of a zeta phase. They normally have fissures at ordinary temperature and are extremely friable. When stock-piled, they break down very rapidly.
  • the present invention consists in a process of fabrication of sintered compounds based on uranium and plutonium, the plutonium content of which is from 15 to 80%, in which, after provision of a uranium-plutonium alloy of the desired plutonium content by any known procedure, the alloy is ground in order to obtain a pulverulent product which is then compressed and sintered with the addition of another element or substance.
  • Metals which can be added to the pulverulent alloy include: molybdenum, niobium, tantalum and zirconium.
  • Nonmetallic elements and substances which can be combined with the alloy include carbon, silicon, nitrogen and hydrogen sulphide.
  • the process according to the invention can be put into eiiect very readily.
  • -It is sufiicient in fact to grind the alloy directly, under an inert atmosphere, in a ball mill, for example.
  • the powders obtained by pulverization of the alloy have an ability to become sintered which is much better than that of mixtures of uranium and plutonium powders obtained by standard processes, for example by calciothermy or by decomposition of the hydrides. They also have the advantage in the case where it is desired to make a mixed compound with a nonmetallic element of conducing directly to the formation of solid solutions of uranium and plutonium compounds.
  • Production of the mixed compound can be effected either in a single stage, that is to say the grinding and reaction "ice of the alloy with the nonmetallic composition are simultaneous, or in two stages, in which preliminary grinding of the alloy in an inert atmosphere is then followed by reaction of the alloy with the nonmetallic compound.
  • Example 1 This example relates to the preparation of a nuclear fuel based upon uranium and plutonium carbides.
  • a uranium-plutonium alloy, the plutonium content of which is 30%, is prepared in an arc furnace;
  • the carbide obtained is ground in a ball mill for 20 minutes in the presence of 1% of naphthalene and 0.5% of nickel by weight; the average grain diameter is then less than 40;;
  • Example 2 This example deals with the preparation of plutonium and uranium mononitride.
  • a uranium-plutonium alloy having a plutonium content of 30% is prepared in an arc furnace;
  • a process for the production of a sintered uraniumplutonium product comprising the steps of grinding to a powder, fragile particles of a uranium-plutonium alloy, the plutonium content of which is from 15 to and compounding said uranium-plutonium powder by compressing and sintering the ground powder in the presence of compounding metallic and nonmetallic materials selected from the group consisting of molybdenum, niobium, tantalum, zirconium, carbon, silicon, nitrogen and hydrogen sulphide.
  • a sintered uranium and plut-onium product prepared according to the process of claim 1.
  • a process for the production of an uranium-plutonium carbide nuclear fuel comprising the steps of grinding under an inert atmosphere fragile particles of a zeta phase containing uranium-plutonium alloy, the plutonium content of which is 30%, in the presence of the stoichiometric quantity of carbon to provide a 40,14 grained powder, compressing this powder at a pressure of about 7.25 1()- p.s.i. into a compact, heating said compact under vacuum at 1200 C. to efiect carburization, grinding the carburized product, compressing the carburized powder and sintering at 1450 C.
  • a process for the production of an uranium-plutonium nitride comprising the steps of grinding a fragile zeta phase containing alloy of uranium and 30% plutonium in an inert atmosphere, introducing a stoichiometric quantity of nitrogen and heating to 350 C. to form nitrides and then sintering the nitn'ded powder.

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

Description

United States Patent 3,275,564 PROCESS OF FABRICATION OF SINTERED COM- 1 :3 am BASED ON URANIUM AND PLUTO- Roger Pascard, Issy-les-Moulineaux, France, assignor to Commissariat a lEnergie Atomique, Paris, France No Drawing. Filed June 11, 1963, Ser. No. 286,958 Claims priority, application France, June 20, 1962, 901,290 9 Claims. (Cl. 252-3011) Uranium and plutonium in the pulverulent state can be compressed and sintered either alone or in the presence of other metallic constituents and can form a sintered alloy which can be used as a fuel element in a nuclear reactor. They can also be combined with another element, for example carbon, nitrogen or silicon, in order to form after heating a novel compound also capable of providing a nuclear fuel by a powder metallurgy method. The production of such sintered products implies that the two base metals are available in the form of powders.
In order to obtain the base metal powders, either the metal oxides are reduced by means of calcium or the hydrides are decomposed.
These methods of preparation have serious disadvantages however.
Although the method of reduction of uranium oxide with calcium is used at present, it cannot be advantageously employed for reducing plutonium oxide, because washing of the production slags with dilute acids is incompatible with the very high oxidizability of plutonium.
Also, although direct action of hydrogen on massive uranium and plutonium provides pulverulent hydrides which can be substituted for the metals in all the applications which are initiated by starting with hydrogen at a slightly elevated temperature, the use of hydrogen in the presence of plutonium is not very desirable because of the danger of explosion which is connected with the use of that gas. Also subsequent fabrication steps necessitates a very slow dehydrogenation stage.
It is known that uranium-plutonium alloys having plutonium contents from 15 to 80% are very fragile, because of the presence of a zeta phase. They normally have fissures at ordinary temperature and are extremely friable. When stock-piled, they break down very rapidly.
The present invention consists in a process of fabrication of sintered compounds based on uranium and plutonium, the plutonium content of which is from 15 to 80%, in which, after provision of a uranium-plutonium alloy of the desired plutonium content by any known procedure, the alloy is ground in order to obtain a pulverulent product which is then compressed and sintered with the addition of another element or substance.
Metals which can be added to the pulverulent alloy include: molybdenum, niobium, tantalum and zirconium.
Nonmetallic elements and substances which can be combined with the alloy include carbon, silicon, nitrogen and hydrogen sulphide.
The process according to the invention can be put into eiiect very readily. -It is sufiicient in fact to grind the alloy directly, under an inert atmosphere, in a ball mill, for example. The powders obtained by pulverization of the alloy have an ability to become sintered which is much better than that of mixtures of uranium and plutonium powders obtained by standard processes, for example by calciothermy or by decomposition of the hydrides. They also have the advantage in the case where it is desired to make a mixed compound with a nonmetallic element of conducing directly to the formation of solid solutions of uranium and plutonium compounds. Production of the mixed compound can be effected either in a single stage, that is to say the grinding and reaction "ice of the alloy with the nonmetallic composition are simultaneous, or in two stages, in which preliminary grinding of the alloy in an inert atmosphere is then followed by reaction of the alloy with the nonmetallic compound. The preparation of other refractory fuel products from these powders, such as carbides for example, .is more readily put into operation than by the reduction of oxides by carbon or carburization of hydrides.
Various examples are given below, by way of illustration only, of the process of manufacture of sintered compounds based on uranium and plutonium in accordance with the invention.
Example 1 This example relates to the preparation of a nuclear fuel based upon uranium and plutonium carbides.
(a) A uranium-plutonium alloy, the plutonium content of which is 30%, is prepared in an arc furnace;
(b) The alloy obtained is ground in a ball mill under an atmosphere of argon for 10 minutes in the presence of the theoretical quantity of carbon for the production of the carbides; the average grain diameter is then less than 40 (c) The powder obtained previously tabletted under a pressure of 7.25 10 p.s.i., in order to efiect the carburization reaction, is then heated under vacuum at 1200 C. for 10 hours;
(d) the carbide obtained is ground in a ball mill for 20 minutes in the presence of 1% of naphthalene and 0.5% of nickel by weight; the average grain diameter is then less than 40;;
(e) The carbide powder and additive are compressed under a pressure of 7.25 x 10- p.s.i.; the apparent density obtained is 9.2 gm./cc.;
(f) The tablets obtained are sintered under vacuum at 1450 C. for 4 hours; the refractory fuel material so obtained has a density of 13.45 gm./cc.
Example 2 This example deals with the preparation of plutonium and uranium mononitride.
(a) A uranium-plutonium alloy having a plutonium content of 30% is prepared in an arc furnace;
(b) The alloy obtained is ground in a :ball mill for 5 minutes under an atmosphere of argon;
(c) After introducing the stoichiometric quantity of nitrogen to form the mononitrides, the mixture is heated for 1 hour at 350 C.;
(d) The powder is then sintered by any known means.
I claim:
1. A process for the production of a sintered uraniumplutonium product comprising the steps of grinding to a powder, fragile particles of a uranium-plutonium alloy, the plutonium content of which is from 15 to and compounding said uranium-plutonium powder by compressing and sintering the ground powder in the presence of compounding metallic and nonmetallic materials selected from the group consisting of molybdenum, niobium, tantalum, zirconium, carbon, silicon, nitrogen and hydrogen sulphide.
2. A process according to claim 1 in which the compounding material is carbon and a carbide of said uranium-plutonium alloy is formed.
3. A process according to claim 1 in which the compounding material is nitrogen and a nitride of said uranium-plutonium alloy is formed.
4. A process according to claim 1 in which the grinding is conducted in an inert atmosphere.
5. A process according to claim 1 in which the compounding material is added during the grinding.
6. A process according to claim 1 in which the compounding material is added to the ground powder.
7. A sintered uranium and plut-onium product prepared according to the process of claim 1.
8. A process for the production of an uranium-plutonium carbide nuclear fuel comprising the steps of grinding under an inert atmosphere fragile particles of a zeta phase containing uranium-plutonium alloy, the plutonium content of which is 30%, in the presence of the stoichiometric quantity of carbon to provide a 40,14 grained powder, compressing this powder at a pressure of about 7.25 1()- p.s.i. into a compact, heating said compact under vacuum at 1200 C. to efiect carburization, grinding the carburized product, compressing the carburized powder and sintering at 1450 C.
9. A process for the production of an uranium-plutonium nitride comprising the steps of grinding a fragile zeta phase containing alloy of uranium and 30% plutonium in an inert atmosphere, introducing a stoichiometric quantity of nitrogen and heating to 350 C. to form nitrides and then sintering the nitn'ded powder.
4 References Cited by the Examiner OTHER REFERENCES Nuclear Reactor Fuel Elements, Metallurgy and Fabrication, Kaufmann, Interscience Publishers, 1962, page 133.
BENJAMIN R. PADGETT, Primary Examiner.
L. DEWAYNE RUTLEDGE, CARL D. QUARFORTH,
Examiners.
A. G. BOWEN, Assistant Examiner.

Claims (1)

1. A PROCESS FFOR THE PRODUCTION OF A SINTERED UNRANIUMPLUTONIUM PRODUCT COMPRISING THE STEPS OF GRINDING TO A POWDER, FRAGILE PARTICLES OF A UNRANIU,-PLUTONIUM ALLOY, THE PLUTONIUM CONTENT OF WHICH IS FROM 15 TO 80%, AND COMPOUNDING SAID URANIUM-PLUTONIUM POWDER BY COMPRESSING AND SINTERING THE GROUND POWDER IN THE PRESENCE OF COMPOUNDING METALLIC AND NONMETALLIC MATERIALS SELECTED FROM THE GROUP CONSISTING OF MOLYBDENUM, NIOBIUM, TANTALUM, ZIRCONIUM, CARBON, SILICON, NITROGEN AND HYDROGEN SULPHIDE.
US286958A 1962-06-20 1963-06-11 Process of fabrication of sintered compounds based on uranium and plutonium Expired - Lifetime US3275564A (en)

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Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3309322A (en) * 1963-11-05 1967-03-14 Commissariat Energie Atomique Uranium monocarbide-plutonium mononitride nuclear fuel
US3418245A (en) * 1966-05-02 1968-12-24 Gen Electric Co Ltd Fuel materials for nuclear reactors
US3806565A (en) * 1971-08-02 1974-04-23 North American Rockwell Method of preparing relatively low density oxide fuel for a nuclear reactor
US20040201002A1 (en) * 2001-07-04 2004-10-14 Laurent Caranoni Method for sulphurizing a uo2 powder and method for making nuclear fuel pellets based on uo2 or mixed oxide (u,pu)o2 oxide with added sulphur
WO2011143293A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2544277A (en) * 1945-06-12 1951-03-06 Amos S Newton Preparation of uranium nitride
US2897077A (en) * 1957-04-10 1959-07-28 Arthur S Coffinberry Plutonium-uranium-titanium alloys
US2902362A (en) * 1957-04-10 1959-09-01 Fred W Schonfeld Plutonium-uranium alloy
US2917383A (en) * 1949-07-29 1959-12-15 Henry A Saller Fabrication of uranium-aluminum alloys
US2926083A (en) * 1957-04-10 1960-02-23 Waber James Thomas Ternary alloy-containing plutonium
US3136629A (en) * 1959-09-08 1964-06-09 Atomic Energy Authority Uk Production of uranium-carbon alloys

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2544277A (en) * 1945-06-12 1951-03-06 Amos S Newton Preparation of uranium nitride
US2917383A (en) * 1949-07-29 1959-12-15 Henry A Saller Fabrication of uranium-aluminum alloys
US2897077A (en) * 1957-04-10 1959-07-28 Arthur S Coffinberry Plutonium-uranium-titanium alloys
US2902362A (en) * 1957-04-10 1959-09-01 Fred W Schonfeld Plutonium-uranium alloy
US2926083A (en) * 1957-04-10 1960-02-23 Waber James Thomas Ternary alloy-containing plutonium
US3136629A (en) * 1959-09-08 1964-06-09 Atomic Energy Authority Uk Production of uranium-carbon alloys

Cited By (22)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3309322A (en) * 1963-11-05 1967-03-14 Commissariat Energie Atomique Uranium monocarbide-plutonium mononitride nuclear fuel
US3418245A (en) * 1966-05-02 1968-12-24 Gen Electric Co Ltd Fuel materials for nuclear reactors
US3806565A (en) * 1971-08-02 1974-04-23 North American Rockwell Method of preparing relatively low density oxide fuel for a nuclear reactor
US20040201002A1 (en) * 2001-07-04 2004-10-14 Laurent Caranoni Method for sulphurizing a uo2 powder and method for making nuclear fuel pellets based on uo2 or mixed oxide (u,pu)o2 oxide with added sulphur
US7309473B2 (en) * 2001-07-04 2007-12-18 Commissariat A L'energic Atomique Method for sulphurizing a UO2 powder and method for making nuclear fuel pellets based on UO2 or mixed oxide (U,Pu)O2 oxide with added sulphur
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
EP3038112A1 (en) * 2010-05-11 2016-06-29 Thorium Power, Inc. Fuel assembly
US10037823B2 (en) 2010-05-11 2018-07-31 Thorium Power, Inc. Fuel assembly
WO2011143172A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly with metal fuel alloy kernel and method of manufacturing thereof
WO2011143293A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly
CN105895178A (en) * 2010-05-11 2016-08-24 钍能源股份有限公司 Fuel assembly
KR101775023B1 (en) 2010-05-11 2017-09-05 토륨 파워 인코포레이티드 Fuel assembly
CN105895178B (en) * 2010-05-11 2018-03-27 钍能源股份有限公司 Fuel assembly
EA023017B1 (en) * 2010-05-11 2016-04-29 Ториум Пауэр, Инк. Fuel assembly
US11862353B2 (en) 2010-05-11 2024-01-02 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
US10991473B2 (en) 2010-05-11 2021-04-27 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11195629B2 (en) 2010-05-11 2021-12-07 Thorium Power, Inc. Fuel assembly
US11837371B2 (en) 2010-05-11 2023-12-05 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11211174B2 (en) 2013-05-10 2021-12-28 Thorium Power, Inc. Fuel assembly
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly

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NL294166A (en)
CH416856A (en) 1966-07-15
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BE633880A (en)
FR1338877A (en) 1963-10-04

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