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公开(公告)号：US11990249B2
公开(公告)日：2024-05-21
申请号：US16518890
申请日：2019-07-22
申请人： TerraPower, LLC
CPC分类号： G21C3/04 , G21C1/026 , G21C3/16 , G21C7/005 , G21C21/08 , G21D3/001 , G21C3/045 , G21C3/047 , G21C3/42 , Y02E30/30
摘要： A fuel element has a ratio of area of fissionable nuclear fuel in a cross-section of the tubular fuel element perpendicular to the longitudinal axis to total area of the interior volume in the cross-section of the tubular fuel element that varies with position along the longitudinal axis. The ratio can vary with position along the longitudinal axis between a minimum of 0.30 and a maximum of 1.0. Increasing the ratio above and below the peak burn-up location associated with conventional systems reduces the peak burn-up and flattens and shifts the burn-up distribution, which is preferably Gaussian. The longitudinal variation can be implemented in fuel assemblies using fuel bodies, such as pellets, rods or annuli, or fuel in the form of metal sponge and meaningfully increases efficiency of fuel utilization.
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2.发明公开公开(公告)号：US20230411024A1
公开(公告)日：2023-12-21
申请号：US17845385
申请日：2022-06-21
申请人： X-Energy, LLC
发明人： Brandon Blamer
CPC分类号： G21C3/045 , G21C3/06 , G01N15/14 , G01N2015/1486
摘要： An optical counter is used in a method and system for producing a nuclear fuel element having a known volume of homogeneously distributed nuclear material. The method includes feeding nuclear fuel particles along a channel having a conveyer configured to transmit the nuclear fuel particles to an exit; driving the conveyer until a target number of nuclear fuel particles exits the channel through the exit; and counting a number of nuclear fuel particles which pass through the exit of the channel with an optical counter. The conveyer is stopped after the target number of nuclear fuel particles exits the channel. The target number of nuclear fuel particles are fed into a mold for shaping the nuclear fuel element, and void space remaining in the mold is filled with a particulate matrix material so as to homogeneously distribute the target number of nuclear fuel particles within the particulate matrix material. The particulate matrix material is then converted into a solid matrix material.
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公开(公告)号：US20230197299A1
公开(公告)日：2023-06-22
申请号：US17925535
申请日：2021-05-19
申请人： Ian Richard SCOTT
发明人： Ian Richard SCOTT , Luke GODFREY
摘要： A molten salt fission reactor. The reactor includes a reactor core, which includes a plurality of fuel tubes. Each fuel tube contains a fuel salt and a gas interface. The fuel salt is a molten salt of one or more fissile isotopes. The gas interface is a surface of the fuel salt in contact with a gas space during operation of the reactor. The reactor also includes a fuel salt cooling system, which is configured to cool the fuel salt. The cooling system includes a heat exchanger and a coolant tank. The coolant tank contains a coolant liquid in which the fuel tubes are at least partially immersed. The heat exchanger is for extracting heat from the coolant liquid. The fuel salt cooling system is configured such that during operation of the reactor, for all points within the fuel salt within each fuel tube except at the respective gas interface:
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公开(公告)号：US20230081699A1
公开(公告)日：2023-03-16
申请号：US17901967
申请日：2022-09-02
申请人： UT-Battelle, LLC
发明人： Kurt A. Terrani , Andrew T. Nelson
摘要： A method for manufacturing a nuclear fuel compact is provided. The method includes forming an additive structure, consolidating a fuel matrix around the additive structure, and thermally processing the fuel matrix to form a fuel compact in which the additive structure is encapsulated therein. The additive structure optionally includes a vertical segment and a plurality of arm segments that extend generally radially from the vertical segment for conducting heat outwardly toward an exterior of the fuel compact. In addition to improving heat transfer, the additive structure may function as burnable absorbers, and may provide fission product trapping.
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公开(公告)号：US11488730B2
公开(公告)日：2022-11-01
申请号：US17065374
申请日：2020-10-07
发明人： Edward J. Lahoda , Peng Xu , Lu Cai
摘要： Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material with a water-resistant layer, the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.
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公开(公告)号：US11456083B2
公开(公告)日：2022-09-27
申请号：US16611328
申请日：2018-04-16
发明人： Simon Middleburgh , Mattias Puide
摘要： A nuclear fuel pellet for a nuclear reactor is disclosed. The pellet comprises a metallic matrix and ceramic fuel particles of a fissile material dispersed in the metallic matrix. The metallic matrix is an alloy consisting of the principle elements U, Zr, Nb and Ti, and of possible rest elements. The concentration of each of the principle elements in the metallic matrix is at the most 50 molar-%.
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公开(公告)号：US11424041B2
公开(公告)日：2022-08-23
申请号：US16835388
申请日：2020-03-31
摘要： Nuclear propulsion fission reactor structure has an active core region including fuel element structures, a reflector with rotatable neutron absorber structures (such as drum absorbers), and a core former conformal mating the outer surface of the fuel element structures to the reflector. Fuel element structures are arranged abutting nearest neighbor fuel element structures in a tri-pitch design. Cladding bodies defining coolant channels are inserted into and joined to lower and upper core plates to from a continuous structure that is a first portion of the containment structure. The body of the fuel element has a structure with a shape corresponding to a mathematically-based periodic solid, such as a triply periodic minimal surface (TPMS) in a gyroid structure. The nuclear propulsion fission reactor structure can be incorporated into a nuclear thermal propulsion engine for propulsion applications, such as space propulsion.
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公开(公告)号：US20220254532A1
公开(公告)日：2022-08-11
申请号：US17697887
申请日：2022-03-17
申请人： FRAMATOME
摘要： A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating (100) a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating (110) a reference secondary PCI margin for the reference pattern; calculating (120) a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating (130) a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.
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9.发明授权公开(公告)号：US11289212B2
公开(公告)日：2022-03-29
申请号：US17032007
申请日：2020-09-25
发明人： James B. Inman , Joshua J. Bergman
摘要： Plurality of layers form a nuclear fission reactor structure, each layer having an inner segment body, an intermediate segment body, and an outer segment body (each segment body separated by an interface). The layers include a plurality of cladding arms having involute curve shapes that spirally radiate outward from a radially inner end to a radially outer end. Chambers in the involute curve shaped cladding arm contain fuel compositions (and/or other materials such as moderators and poisons). The design of the involute curve shaped cladding arms and the composition of the materials conform to neutronic and thermal management requirements for the nuclear fission reactor and are of sufficiently common design and/or have sufficiently few variations as to reduce manufacturing complexity and manufacturing variability.
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公开(公告)号：US20210304905A1
公开(公告)日：2021-09-30
申请号：US17200028
申请日：2021-03-12
申请人： Kwang-young Lim , Tae-sik Jung , Yeon-su Na , Min-jae Joo , Seung-jae Lee , Yoon-ho Kim
发明人： Kwang-young Lim , Tae-sik Jung , Yeon-su Na , Min-jae Joo , Seung-jae Lee , Yoon-ho Kim
摘要： The present disclosure relates to a pellet containing an oxide additive to improve a nuclear-fission-gas-adsorption ability of a uranium-dioxide pellet used as nuclear fuel and increase the grain size thereof, and to a method of manufacturing the same. A La2O3—Al2O3—SiO2 sintering additive is added to uranium dioxide so that mass movement is accelerated due to the liquid phase generated during sintering of the uranium-dioxide pellet, which promotes the growth of grains thereof. Further, since less volatilization occurs during sintering due to the low vapor pressure of the liquid phase, efficient additive performance is exhibited, so the liquid phase surrounding the grain boundary effectively adsorbs cesium, which is a nuclear fission gas.
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