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公开(公告)号：US2900315A
公开(公告)日：1959-08-18
申请号：US32603552
申请日：1952-12-15
申请人： OHLINGER LEO A
发明人： OHLINGER LEO A
CPC分类号： B23K20/02 , B21C37/154 , B23K2201/06 , G21C3/04 , G21C21/02 , Y02E30/40 , Y10T29/4902 , Y10T29/49915
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公开(公告)号：US2885335A
公开(公告)日：1959-05-05
申请号：US50752455
申请日：1955-05-11
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公开(公告)号：US12080436B2
公开(公告)日：2024-09-03
申请号：US18210437
申请日：2023-06-15
发明人： Mehul Shah , Rida Milany , Koroush Shirvan
摘要： Thorium-based fuel bundles according to one or more embodiments of the present invention provide a fresh fuel bundle comprising a first ring of fuel pins and a second ring of fuel pins. Each ring fuel pin has a fuel composition comprising uranium and thorium. The first ring fuel pins differ from the second ring fuel pins in each of the thorium wt %, uranium wt %, and 235U enrichment.
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公开(公告)号：US20240266078A1
公开(公告)日：2024-08-08
申请号：US18163415
申请日：2023-02-02
发明人： Jeffrey SHOUP , Yuriy ALESHIN , David M. GROSS , Joshua J. DONOVAN , Jurie J. VAN WYK , Jeffrey M. PARKS
摘要： Disclosed is nuclear reactor fuel rod for use in a nuclear reactor. The nuclear reactor fuel rod comprises a sleeve defining a longitudinal axis. The sleeve includes a first end portion and a second end portion. The nuclear reactor fuel rod further includes a first end cap mechanically coupled to the first end portion of the sleeve and a second end cap mechanically coupled to the second end portion of the sleeve. The second end cap is configured to slide along the longitudinal axis relative to the sleeve. The nuclear reactor fuel rod further includes a fuel compact located inside of the sleeve between the first end cap and the second end cap.
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公开(公告)号：US12051515B2
公开(公告)日：2024-07-30
申请号：US17275424
申请日：2019-09-12
申请人： FRAMATOME
发明人： Christian Royere , Mathieu Segond
IPC分类号： G21D3/00 , G21C3/04 , G21C9/00 , G21C17/108
CPC分类号： G21D3/001 , G21C3/047 , G21C9/00 , G21C17/108
摘要： A method for protecting a nuclear reactor includes reconstructing a maximum linear power density released among the fuel rods of the nuclear fuel assemblies of the core; calculating the thermomechanical state and the burnup fraction of the rods; calculating a mechanical stress or deformation energy density in the cladding of one of the rods by using the said reconstructed maximum linear power density, the calculated thermomechanical states and the calculated burnup fractions, by means of a meta-model of a thermomechanical code; comparing the calculated mechanical stress or the calculated deformation energy density with a respective threshold; and stopping the nuclear reactor if the calculated mechanical stress or the calculated deformation energy density exceeds the respective threshold.
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公开(公告)号：US11942229B2
公开(公告)日：2024-03-26
申请号：US16851142
申请日：2020-04-17
发明人： Craig D. Gramlich
摘要： Fission reactor has a cladding encasing a heat generating source including a fissionable nuclear fuel composition. The heat generating source is offset from the surface of the cladding and molten metal is located within the void space formed by the offset. As a liquid, the molten metal will flow and occupy any contiguous network of void space within the fuel cavity and provides thermal transfer contact between the heat generating source and the cladding. The cladding separates the heat generating source and the molten metal from the primary coolant volume.
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公开(公告)号：US11935662B2
公开(公告)日：2024-03-19
申请号：US16459764
申请日：2019-07-02
发明人： Yun Long , Peng Xu , Edward J. Lahoda
摘要： An elongate fuel element is described that has a silicon carbide cladding enclosing a fuel, such as UO2, wherein the fuel is dimensioned relative to the cladding to define gaps at each lateral end of the enclosure sufficiently large such that upon swelling in use, the fuel does not increase the strain on the cladding beyond the limits of the claddings strain tolerance. The lateral gaps at the ends of the fuel allow lateral expansion during swelling that reduces the strain on the cladding.
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公开(公告)号：US11929183B2
公开(公告)日：2024-03-12
申请号：US18195112
申请日：2023-05-09
发明人： Mehul Shah , Rida Milany , Koroush Shirvan
摘要： Thorium-based fuel bundles according to one or more embodiments of the present invention are used in existing PHWR reactors (e.g., Indian 220 MWe PHWR, Indian 540 MWe PHWR, Indian 700 MWe PHWR, CANDU 300/600/900) in place of conventional uranium-based fuel bundles, with little or no modifications to the reactor. The fuel composition of such bundles is 60+ wt % thorium, with the balance of fuel provided by low-enriched uranium (LEU), which has been enriched to 13-19.95% 235U. According to various embodiments, the use of such thorium-based fuel bundles provides (1) 100% of the nominal power over the entire life cycle of the core, (2) high burnup, and (3) non-proliferative spent fuel bundles having a total isotopic uranium concentration of less than 12 wt %. Reprocessing of spent fuel bundles is also avoided.
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公开(公告)号：US11817225B2
公开(公告)日：2023-11-14
申请号：US17852434
申请日：2022-06-29
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：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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