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公开(公告)号：US11932540B2
公开(公告)日：2024-03-19
申请号：US16765987
申请日：2018-11-28
发明人： German Cota-Sanchez
IPC分类号： B32B9/00 , C01B32/159 , C01B32/166 , G21C3/07 , G21C3/17 , G21C3/20
CPC分类号： C01B32/159 , C01B32/166 , G21C3/07 , G21C3/17 , G21C3/20 , C01B2202/02 , C01B2202/36 , C01P2002/72 , C01P2002/82 , C01P2002/84 , C01P2002/88 , C01P2002/89 , C01P2004/03 , C01P2004/04 , C01P2006/10 , Y10T428/30
摘要： A nuclear fuel element for use in a nuclear reactor may include a plurality of metal fuel sheaths extending along a longitudinal fuel element axis and spaced apart from each other, the plurality of fuel sheaths comprising a first fuel sheath having an inner surface, an opposing outer surface and a hollow interior configured to receive nuclear fuel material. A carbon coating may be on the inner surface of the first fuel sheath. The carbon coating may include more than 99.0% wt of a carbon material including more than 20% wt of carbon nanotubes and less than about 0.01% wt of organic contaminants.
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公开(公告)号：US20230298772A1
公开(公告)日：2023-09-21
申请号：US18018543
申请日：2021-07-29
申请人： FRAMATOME
发明人： Pierre BARBERIS , Jeremy BISCHOFF , Karl BUCHANAN
摘要： A nuclear fuel cladding element comprises a substrate made of a material containing zirconium and a protective coating covering the substrate on the outside. The protective coating is being made of a material containing chromium, and has a columnar microstructure composed of columnar grains and having on the outer surface thereof a microdroplet density of less than 100 per mm2.
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公开(公告)号：US11735326B2
公开(公告)日：2023-08-22
申请号：US17601886
申请日：2021-03-08
申请人： OKLO INC.
发明人： Jacob DeWitte , Caroline Cochran , Patrick Everett , John Hanson , Joshua G. Richard , Alex Renner , Nathan Graff , David Hawn
IPC分类号： G21C15/257 , G21C3/20 , G21C1/32 , G21C3/38
CPC分类号： G21C15/257 , G21C1/326 , G21C3/20 , G21C1/322 , G21C3/38
摘要： Fuel, heat exchangers, and instrumentation for nuclear reactors are disclosed. A nuclear power system includes a plurality of nuclear fuel elements, each of the nuclear fuel elements including an annulus; and a plurality of heat pipes, each of the plurality of heat pipes configured to pass through the annulus of a respective one of the nuclear fuel elements in conductive thermal contact with the respective nuclear fuel element. A nuclear instrumentation module includes an assembly of optical fibers, each optical fiber comprising one or more sensors and configured for removable installation at one of the plurality of heat pipes. A heat exchanger includes a heat pipe including an evaporating region and a condensing region; and a tube bundle configured to wrap around the condensing region of the heat pipe and including one or more adjacent, parallel tubes, each tube forming a helix that is coaxial to the heat pipe.
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公开(公告)号：US11587689B2
公开(公告)日：2023-02-21
申请号：US17072903
申请日：2020-10-16
摘要： A nuclear fuel element includes a core comprising a fissile element and an additional element. A protective structure surrounds the core and comprises at least a first material surrounding the nuclear fuel. The first material comprises the fissile element and the additional element and comprises a greater than stoichiometric amount of the additional element. An outer portion of the nuclear fuel element comprises a metal. Related nuclear fuel elements, and related methods are also disclosed.
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公开(公告)号：US20230036331A1
公开(公告)日：2023-02-02
申请号：US17758443
申请日：2021-01-08
摘要： A nuclear fuel assembly and a method of manufacture thereof are provided. The method comprises depositing a thermally conductive layer onto at least a portion of at least two nuclear fuel layers to create at least two at least partially coated layers. The method comprises stacking the at least two coated layers and bonding the at least two coated layers to form a nuclear fuel assembly.
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公开(公告)号：US11551822B2
公开(公告)日：2023-01-10
申请号：US17473433
申请日：2021-09-13
发明人： Edward J. Lahoda , Peng Xu , Robert L. Oelrich, Jr. , Hemant Shah , Jonathan Wright , Lu Cai
摘要： A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.
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公开(公告)号：US11545273B2
公开(公告)日：2023-01-03
申请号：US17022866
申请日：2020-09-16
发明人： Frédéric Schuster , Fernando Lomello , Francis Maury , Alexandre Michau , Raphaël Boichot , Michel Pons
IPC分类号： G21C3/20 , G21C3/34 , G21C5/18 , G21C7/10 , G21C3/07 , C23C16/02 , C23C16/04 , C23C16/34 , C23C16/448 , C23C16/56 , G21C3/326 , G21C3/36
摘要： A composite nuclear reactor component comprises a support and a protective layer (2). The support contains a substrate (1) based on a metal. The substrate is coated with an interposed layer (3) positioned between the substrate (1) and the protective layer (2). The protective layer (2) is composed of a material which comprises amorphous chromium carbide. The nuclear reactor component provides for improved resistance to oxidation, hydriding, and/or migration of undesired material.
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公开(公告)号：US11527333B2
公开(公告)日：2022-12-13
申请号：US17216676
申请日：2021-03-30
发明人： Young Wook Kim , Jung Hye Eom , Yu Kwang Seo , Seung Jae Lee
IPC分类号： G21C3/62 , C04B35/626 , C04B35/628 , C04B35/634 , C04B35/565 , C04B35/632 , C04B35/645 , C04B38/00 , G21C3/20 , G21C21/04
摘要： The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic particles coated with the substance which includes, as a main ingredient, a silicon carbine derived from a precursor of the silicon carbide wherein a condition of ΔLc>ΔLm at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔLc and the sintering shrinkage of the silicon carbide matrix is ΔLm; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.
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公开(公告)号：US11139086B2
公开(公告)日：2021-10-05
申请号：US15834922
申请日：2017-12-07
申请人： HOWE INDUSTRIES, LLC
发明人： Troy M. Howe , Steven D. Howe
IPC分类号： G21C3/36 , G21C3/20 , G21C15/06 , G21C5/18 , G21C5/16 , G21C3/64 , B64G1/40 , G21C5/12 , G21C3/62
摘要： A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.
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公开(公告)号：US10811146B2
公开(公告)日：2020-10-20
申请号：US16337647
申请日：2017-09-28
发明人： Frédéric Schuster , Fernando Lomello , Francis Maury , Alexandre Michau , Raphaël Boichot , Michel Pons
IPC分类号： G21C5/18 , C23C16/02 , C23C16/04 , C23C16/34 , C23C16/448 , C23C16/56 , G21C3/20 , G21C3/326 , G21C3/34 , G21C7/10
摘要： Process for manufacturing a nuclear component comprising i) a support containing a substrate based on a metal (1), the substrate (1) being coated or not coated with an interposed layer (3) positioned between the substrate (1) and at least one protective layer (2) and ii) the protective layer (2) composed of a protective material comprising amorphous chromium carbide; the process comprising a step a) of vaporizing a mother solution followed by a step b) of depositing the protective layer (2) onto the support via a process of chemical vapor deposition of an organometallic compound by direct liquid injection (DLI-MOCVD).
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