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21.发明申请公开(公告)号：US20210271793A1
公开(公告)日：2021-09-02
申请号：US17142286
申请日：2021-01-06
发明人： Ross Evan PIVOVAR
摘要： A method is used to design nuclear reactors using design variables and metric variables. A user specifies ranges for the design variables and target values for the metric variables. A set of design parameter samples are selected. For each sample, the method runs three processes, which compute metric variables to thermal-hydraulics, neutronics, and stress. The method applies a cost function to each sample to compute an aggregate residual of the metric variables compared to the target values. The method trains a machine learning model using the samples and the computed aggregate residuals. The method shrinks the range for each design variable according to correlation between the respective design variable and estimated residuals using the machine learning model. These steps are repeated until a sample having a smallest residual is unchanged for multiple iterations. The method then uses the final machine learning model to assess relative importance of each design variable.
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公开(公告)号：US20210082587A1
公开(公告)日：2021-03-18
申请号：US17024051
申请日：2020-09-17
摘要： A control drum system for a nuclear reactor including a reactor core, including an ex-core reflector including a plurality of cylindrical apertures, a plurality of control drum assemblies, each control drum assembly including a drive shaft, a drum cylinder affixed to a bottom end of the drive shaft, and a planetary gear attached to a top end of the drive shaft, wherein each drum cylinder is rotatably received in a cylindrical aperture, a first control drum drive motor operably connected to a first control drum assembly, and an annular ring gear that is operably connected to the planetary gear of each of the control drum assemblies so that all the control drum assemblies rotate simultaneously.
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公开(公告)号：US20200234834A1
公开(公告)日：2020-07-23
申请号：US16731867
申请日：2019-12-31
摘要： A nuclear fuel assembly for a nuclear reactor core including at least one fuel cartridge having a lattice structure including an outer wall defining an interior volume, at least one flow channel extending through the interior volume of the lattice structure, at least one lattice site disposed in the interior of the lattice structure; and at least one fuel compact disposed within a corresponding one of the at least one lattice site. A cross-sectional shape of the at least one fuel compact is the same as a cross-sectional shape of the corresponding one of the at least one lattice site.
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公开(公告)号：US12094618B2
公开(公告)日：2024-09-17
申请号：US16731867
申请日：2019-12-31
CPC分类号： G21C3/328 , G21C5/06 , Y10S376/903
摘要： A nuclear fuel assembly for a nuclear reactor core including at least one fuel cartridge having a lattice structure including an outer wall defining an interior volume, at least one flow channel extending through the interior volume of the lattice structure, at least one lattice site disposed in the interior of the lattice structure; and at least one fuel compact disposed within a corresponding one of the at least one lattice site. A cross-sectional shape of the at least one fuel compact is the same as a cross-sectional shape of the corresponding one of the at least one lattice site.
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公开(公告)号：US20240266077A1
公开(公告)日：2024-08-08
申请号：US18386031
申请日：2023-11-01
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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26.发明授权公开(公告)号：US11990248B2
公开(公告)日：2024-05-21
申请号：US16999244
申请日：2020-08-21
CPC分类号： G21C17/102 , G21C3/04 , G21C19/30 , B64G1/408 , B64G1/422
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 upper and lower core plates to from a continuous structure that is a first portion of the containment 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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27.发明公开公开(公告)号：US20240127974A1
公开(公告)日：2024-04-18
申请号：US18386378
申请日：2023-11-02
摘要： Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons ≤0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.
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公开(公告)号：US20230367933A1
公开(公告)日：2023-11-16
申请号：US18142107
申请日：2023-05-02
发明人： Ross PIVOVAR
IPC分类号： G06F30/23
CPC分类号： G06F30/23 , G06F2111/10
摘要： A method is provided for using a hierarchical polynomial model for physics simulation. The method includes obtaining coupled equations for a physics simulation. The coupled equations have variables and boundary conditions that constrain the variables. The method also includes generating meshes corresponding to the coupled equations. The method iteratively solves for the boundary conditions that depend on the variables within the meshes to convergence to improve numerical stability of the physics simulation, including: (i) solving for each variable in a first mesh, while holding the other meshes to a weak convergence, to obtain a first solution; (ii) applying the first solution to resolve a second mesh, to obtain a second solution; and (iii) generating a hierarchical polynomial based on the second solution. The hierarchical polynomial is a functional form of a pre-determined physics equation. The method also (iv) computes new boundary conditions for resolving the meshes, using the hierarchical polynomial.
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公开(公告)号：US20230326618A1
公开(公告)日：2023-10-12
申请号：US18204517
申请日：2023-06-01
发明人： Eric A. BARRINGER , Russell R. JENSEN , Jeremy L. GUSTAFSON , Matt ALES , Joshua J. BERGMAN , Ryan T. SWANSON , Jonathan K. WITTER , Danny GALICKI , James B. INMAN , Matt KRECICKI , Roger RIDGEWAY
摘要： Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. Fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.
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公开(公告)号：US20230282374A1
公开(公告)日：2023-09-07
申请号：US18118206
申请日：2023-03-07
IPC分类号： G21C3/322
CPC分类号： G21C3/322
摘要： Fuel bundle has plurality of twisted ribbon fuel rodlets arranged hexagonal packing or circle packing arrangement in a reactor core encased in a multilayer casing. Arrangement of twisted ribbon fuel rodlets is facilitated by rodlet seating fixture with seating surface having a plurality of protrusions that form a receiving space for ends of the twisted ribbon fuel rodlets. Manufacture of the fuel bundle incorporates fiber manufacturing technologies and, optionally, infiltration of spaces in the reactor core by infiltrant. Twisted ribbon fuel rodlet manufacturing system has sub-systems that impart twist periodicity to extruded ribbons, inspect twisted extruded ribbons, and cut twisted extruded ribbons to length. Inspection sorts twisted ribbon fuel rodlets as well as provides feedback to adjust operation of sub-systems. The fuel bundle (and optional fuel bundle support) can be incorporated into a fuel assembly of nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.
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