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1.发明申请公开(公告)号：US20180261346A1
公开(公告)日：2018-09-13
申请号：US15954534
申请日：2018-04-16
申请人： FRAMATOME
CPC分类号： G21C21/02 , B22F3/10 , B22F5/00 , B22F9/04 , G21C3/02 , G21C3/07 , G21C3/60 , G21G4/08 , Y02E30/38 , Y10T29/49828
摘要： A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The core has a low-enriched uranium loading strictly higher than 3.0 gU/cm3 and includes less than 10 wt % of aluminium phase and/or aluminium compounds other than UAl2 phase, than UAl3 phase, and than UAl4 phase. A corresponding nuclear fuel product is also provided.
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公开(公告)号：US20180197640A1
公开(公告)日：2018-07-12
申请号：US15404477
申请日：2017-01-12
CPC分类号： G21C3/332 , G21C3/26 , G21C3/322 , G21C3/326 , G21C3/3267 , G21C3/3305 , G21C3/334 , G21C3/34 , G21C7/117 , G21C7/12 , G21C7/20 , G21C9/02 , Y02E30/38 , Y02E30/39
摘要： A nuclear fuel assembly comprising a plurality of control rod guide assemblies. At least one of the control rod guide assemblies includes a guide tube having an axial dimension, the guide tube being supported by the plurality of grids and extending axially between the top nozzle and the bottom nozzle, the guide tube having an upper portion having a first radius and a lower portion having a second radius less than the first radius, and an external dashpot tube disposed around a portion of the lower portion in an area beginning at the bottom grid and extending toward the top nozzle.
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公开(公告)号：US09966156B2
公开(公告)日：2018-05-08
申请号：US15535071
申请日：2015-12-17
发明人： Stéphane Vaudez
CPC分类号： G21C21/02 , C01G56/007 , C01P2002/50 , C01P2006/44 , C04B35/50 , C04B35/51 , C04B35/62204 , C04B35/64 , C04B2235/3229 , C04B2235/6562 , C04B2235/6565 , C04B2235/6567 , C04B2235/658 , C04B2235/6582 , C04B2235/6588 , C04B2235/663 , C04B2235/721 , C04B2235/77 , G21C3/04 , G21C3/62 , G21C3/623 , G21C2003/045 , Y02E30/38
摘要： The present invention relates to a process for sintering a compacted powder of at least one oxide of a metal selected from an actinide and a lanthanide, this process comprising the following successive steps, carried out in a furnace and under an atmosphere comprising an inert gas, dihydrogen and water: (a) a temperature increase from an initial temperature TI up to a hold temperature TP, (b) maintaining the temperature at the hold temperature TP, and (c) a temperature decrease from the hold temperature TP down to a final temperature TF, in which the P(H2)/P(H2O) ratio is such that: 500
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公开(公告)号：US20180040385A1
公开(公告)日：2018-02-08
申请号：US15549534
申请日：2016-02-11
申请人： Candu Energy Inc.
发明人： In Seob Hong , Mohamed Dahmani
摘要： Fuel bundles for nuclear reactors are provided, and can include a fuel element containing U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element. Fuel bundles for nuclear reactors are also provided that include fuel elements having inner elements and outer elements, wherein at least one of the inner elements includes a homogeneous mixture of a fissile material and at least two neutron absorbers. Fuel elements for nuclear reactors are also provided, and can include U-233, U-235, PU-239, and/or PU-241 fissile material, along with at least two neutron absorbers consisting of Gd, Dy, Hf, Er, and/or Eu, wherein the fissile material(s) and the at least two neutron absorbers are homogeneously mixed in the fuel element.
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公开(公告)号：US20170352437A1
公开(公告)日：2017-12-07
申请号：US12879612
申请日：2010-09-10
申请人： Russell Patrick Higgins , Vernon W. Mills , David Grey Smith , Gerald Anthony Luciano , Roger Howard Van Slyke , William Earl Russell, II , Bradley D. Bloomquist
发明人： Russell Patrick Higgins , Vernon W. Mills , David Grey Smith , Gerald Anthony Luciano , Roger Howard Van Slyke , William Earl Russell, II , Bradley D. Bloomquist
摘要： One embodiment provides a multi-segment rod that includes a plurality of rod segments. The rod segments are removably mated to each other via mating structures in an axial direction. An irradiation target is disposed within at least one of the rod segments, and at least a portion of at least one mating structure includes one and/or more combinations of neutron absorbing materials.
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公开(公告)号：US20170330637A1
公开(公告)日：2017-11-16
申请号：US15513711
申请日：2015-09-17
发明人： Uffe BERGMANN , Jonas AURÉN , Lars-Erik JOHANSSON
摘要： A fuel assembly for a nuclear power boiling water reactor, including: a fuel channel defining a central fuel channel axis, fuel rods, each having a central fuel rod axis, at least 3 water channels for non-boiling water, each water channel having a central water channel axis and each water channel having a larger cross-sectional area than the cross-sectional area of (the average) fuel rod. The fuel rods comprise a first group of full length fuel rods and a second group of shorter fuel rods. The fuel assembly comprises at least 5 fuel rods which belong to said second group and which are positioned such that the central fuel rod axis of each of these at least 5 fuel rods is closer to the central fuel channel axis than any of the water channel axes of the water channels.
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公开(公告)号：US20170301418A1
公开(公告)日：2017-10-19
申请号：US15380473
申请日：2016-12-15
IPC分类号： G21C3/54
摘要： A salt composition for use as a fuel in a nuclear reactor is provided. The salt composition can include carrier salts having mixtures of one or more chloride salts or one or more chloride salts and one or more fluoride salts and fuel salts including one or more chloride salts. The carrier salts can include alkali and/or alkaline earth cations, while the fuel salts can include actinide cations. The salt composition has a lower melting temperature, less corrosive redox properties, and allows proliferation-safe retention of actinides and concurrent removal of some fission products, as compared to other salts employed in molten salt reactors. Optionally, the salt composition can include one or more metal halides for further decreasing the melting point and/or increasing the boiling point of the composition, thereby increasing the range of the liquid phase of the salt composition.
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公开(公告)号：US09786391B2
公开(公告)日：2017-10-10
申请号：US15044747
申请日：2016-02-16
申请人： X-Energy, LLC.
发明人： Peter Pappano , Martin van Staden
CPC分类号： G21C3/28 , B29C64/165 , B33Y10/00 , B33Y80/00 , G21C1/07 , G21C3/42 , G21C3/58 , G21C3/62 , G21C21/02 , G21C21/14 , Y02E30/36 , Y02E30/38
摘要： A method of manufacturing nuclear fuel elements may include: forming a graphite base portion of the fuel element; depositing a first layer of graphite spheres on the base portion; depositing a first layer of fuel, burnable poison and/or breeder particles on the first layer of graphite spheres; forming a second layer of graphite spheres on the first layer of particles; depositing a second layer of fuel, burnable poison and/or breeder particles on the second layer of graphite spheres; and forming a graphite cap portion of the fuel element. Fuel, burnable poison and/or breeder particles of the first layer may be are spaced apart by substantially the same distance, and fuel, burnable poison and/or breeder particles of the second layer may be spaced apart by substantially the same distance. The fuel element may be a spherical fuel pebble. The fuel particles may be tri-structural-isotropic (TRISO) particles without an overcoat.
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公开(公告)号：US20170287574A1
公开(公告)日：2017-10-05
申请号：US15509056
申请日：2015-04-24
摘要： A method of making a nuclear fuel pellet for a nuclear power reactor. The method includes providing a nuclear fuel material in powder form, providing an additive, forming a so-called green pellet, wherein said additive is added either to said nuclear fuel material in powder form or to the green pellet, sintering the green pellet, wherein said additive is such that it causes larger grains in the nuclear fuel pellet, and wherein said additive is made of or includes a substance which causes the larger grains and which substantially leaves at least an outer portion of the pellet before and/or during the sintering step.
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公开(公告)号：US20170271034A1
公开(公告)日：2017-09-21
申请号：US15509037
申请日：2015-04-24
发明人： Hans WIDEGREN
摘要： A method of making a nuclear fuel pellet for a nuclear power reactor. The method includes providing a nuclear fuel material in powder form, pressing the powder such that a so-called green pellet is obtained, providing a liquid that comprises an additive which is to be added to the green pellet, contacting the green pellet with the liquid such that the liquid, with the additive, penetrates into the pellet, and sintering the so treated green pellet, wherein the additive is such that larger grains in the nuclear fuel material are obtained with the additive.
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