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1. 发明公开

US20230282373A1 FUEL BUNDLE WITH TWISTED RIBBON FUEL RODLETS FOR NUCLEAR THERMAL PROPULSION APPLICATIONS, STRUCTURES FOR MANUFACTURE, AND METHODS OF MANUFACTURE 审中-公开
公开(公告)号：US20230282373A1
公开(公告)日：2023-09-07
申请号：US18118193
申请日：2023-03-07
申请人： BWXT Advanced Technologies LLC
发明人： Benjamin D. FISHER , John R. SALASIN
IPC分类号： G21C3/322 , G21D5/02 , B64G1/40
CPC分类号： G21C3/322 , G21D5/02 , B64G1/408
摘要： Fuel bundle has plurality of twisted ribbon fuel rodlets arranged in 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.

2. 发明公开

US20230162875A1 CONTROL ROD DAMPING SYSTEM 审中-公开
公开(公告)号：US20230162875A1
公开(公告)日：2023-05-25
申请号：US18104764
申请日：2023-02-01
申请人： NuScale Power, LLC
发明人： Ross Douglas Snuggerud
IPC分类号： G21C7/20 , G21C7/11 , G21C7/117 , G21C3/322
CPC分类号： G21C7/20 , G21C3/322 , G21C7/11 , G21C7/117 , G21C3/3315
摘要： A damping area or “dash pot” on the upper ends of control rods absorb energy from dropped control rod assemblies without narrowing the diameter of guide tubes. As a result, coolant can freely flow through the guide tubes reducing boiling water issues. The dampening area reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tubes decelerating the control rods when entering a top end of the guide tubes. In another example, the dampening area may be located on a drive shaft. The dampening area may have a larger diameter than an opening in a drive shaft support member that decelerates the drive shaft when dropped by a drive mechanism.

3. 发明授权

US10878968B2 Channel box 有权
公开(公告)号：US10878968B2
公开(公告)日：2020-12-29
申请号：US15411151
申请日：2017-01-20
申请人： KABUSHIKI KAISHA TOSHIBA
发明人： Shoko Suyama , Masaru Ukai , Masayuki Uchihashi , Hideaki Heki
IPC分类号： G21C3/324 , G21C3/322 , C04B35/628 , C04B35/565
CPC分类号： G21C3/324 , G21C3/322 , C04B35/565 , C04B35/628 , C04B35/62839 , C04B35/62868 , Y02E30/30
摘要： A channel box in an embodiment includes a tubular portion. The tubular portion includes a first tubular layer, a second tubular layer, and an intermediate tubular layer. The first tubular layer contains silicon carbide as a major component. The second tubular layer is in parallel to and surrounds or is surrounded by the first tubular layer and contains silicon carbide fibers and silicon carbide complexed with the silicon carbide fibers. The intermediate tubular layer is disposed between the first tubular layer and the second tubular layer and contains a solid lubricant.

4. 发明申请

US20180356021A1 CROSS-OVER FLUID COUPLING 审中-公开
公开(公告)号：US20180356021A1
公开(公告)日：2018-12-13
申请号：US15735374
申请日：2016-06-22
申请人： ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE
发明人： James M. King , Andrew B. Kittmer , Terry J. Schaubel
IPC分类号： F16L39/00 , G21C21/00 , F16L59/065 , F16L37/088
CPC分类号： F16L39/005 , F16L9/19 , F16L9/20 , F16L23/12 , F16L37/088 , F16L59/065 , F28D7/106 , F28F9/26 , F28F13/06 , F28F2250/04 , F28F2250/10 , G21C1/20 , G21C3/322 , G21C3/328 , G21C15/02 , G21C21/00
摘要： A cross-over fluid coupling includes a first coupling end and a second coupling end. A plurality of first conduits have inner ends disposed toward the first coupling end and outer ends spaced apart from the inner end toward the second coupling end and being outboard of the inner end. A plurality of second conduits have outer ends that are disposed toward the first coupling end and positioned laterally outboard of the inner end of at least one of the first conduits, and inner ends that are spaced apart from the outer end toward the second coupling end in the axial direction and is laterally inboard of the outer end of the at least one of the first conduits.

5. 发明申请

US20180090237A1 TRANSPORTABLE SUB-CRITICAL MODULES FOR POWER GENERATION AND RELATED METHODS 审中-公开
公开(公告)号：US20180090237A1
公开(公告)日：2018-03-29
申请号：US15565164
申请日：2016-04-12
申请人： Claudio Filippone
发明人： Claudio Filippone
IPC分类号： G21D5/02 , G21C3/06 , G21C1/30 , G21C3/16 , G21C15/06 , G21C3/322
CPC分类号： G21D5/02 , G21C1/30 , G21C1/32 , G21C3/045 , G21C3/06 , G21C3/16 , G21C3/322 , G21C7/30 , G21C11/02 , G21C15/04 , G21C15/06 , Y02E30/40
摘要： Various embodiments of a transportable nuclear power generator having a plurality of subcritical power modules are disclosed. Each of the plurality of subcritical power modules includes a fuel cartridge, a power conversion unit, and a housing substantially enclosing the fuel cartridge and the power conversion unit. The fuel cartridge contains a nuclear fuel and has a proximal end and a distal end. The power conversion unit includes a compressor turbine disposed at the proximal end of the fuel cartridge and a power turbine disposed at the distal end of the fuel cartridge. At least one of the plurality of subcritical power modules is movable with respect to the other of the plurality of subcritical power modules between a first position and a second position to control criticality of the nuclear fuel contained in the fuel cartridges of the plurality of subcritical power modules.

6. 发明申请

US20170330638A1 NUCLEAR REACTOR FUEL ROD AND FUEL ASSEMBLY HAVING BUNDLED SAME 审中-公开
公开(公告)号：US20170330638A1
公开(公告)日：2017-11-16
申请号：US15529663
申请日：2014-11-26
申请人： HITACHI, LTD.
发明人： Ryou ISHIBASHI , Kinya AOTA , Xudong ZHANG , Hideki KITA , Seiji YAMASHITA
IPC分类号： G21C3/322 , G21C15/243 , G21C5/12
CPC分类号： G21C3/322 , B23K1/0008 , B23K1/18 , B23K1/19 , B23K20/026 , B23K20/16 , B23K20/233 , B23K2101/06 , B23K2103/52 , C04B37/006 , C04B2235/9607 , C04B2235/9669 , C04B2237/083 , C04B2237/122 , C04B2237/126 , C04B2237/127 , C04B2237/16 , C04B2237/365 , C04B2237/38 , C04B2237/708 , C04B2237/72 , C04B2237/765 , C04B2237/84 , G21C3/07 , G21C3/10 , G21C3/326 , G21C5/126 , G21C15/243 , G21C21/02 , Y02E30/40
摘要： A nuclear reactor fuel rod is a fuel rod for a light-water reactor. The nuclear reactor fuel rod includes a fuel cladding tube and an end plug, both of which are formed of a silicon carbide material. A bonding portion between the fuel cladding tube and the end plug is formed by brazing with a predetermined metal bonding material interposed, and/or by diffusion bonding. The predetermined metal bonding material has a solidus temperature of 1200° C. or higher. An outer surface of the bonding portion, and a portion of an outer surface of the fuel cladding tube and the end plug, which is adjacent to the outer surface of the bonding portion are covered by bonding-portion coating formed of a predetermined coating metal. The predetermined metal bonding material and the predetermined coating metal have an average linear expansion coefficient which is less than 10 ppm/K.

7. 发明申请

US20170309352A1 FUEL ASSEMBLY FOR BOILING WATER REACTOR 审中-公开
公开(公告)号：US20170309352A1
公开(公告)日：2017-10-26
申请号：US15513696
申请日：2015-09-14
申请人： WESTINGHOUSE ELECTRIC SWEDEN AB
发明人： Sture HELMERSSON , Markus MÅNSSON , Anders SÖDERLUND
IPC分类号： G21C3/336 , G21C3/20 , G21C19/10 , G21C3/322
CPC分类号： G21C3/33 , G21C3/322 , G21C3/3225 , Y02E30/31 , Y02E30/38
摘要： A fuel assembly for a boiling water reactor, having fuel rods, a tie plate, a handle device, and at least two water rods attached to the tie plate and to the handle device. A plurality of spacers, define first passages for some of the fuel rods, and second passages for the water rods. Each water rod comprises a tube part attached to the tie plate, and a solid part attached to the handle device. The tube part permits a flow of coolant. The spacers include primary spacers and a secondary spacer. The primary spacers are attached to the tube parts. The tie plate, the water rods, the primary spacers and the handle device form a support structure carrying the weight of the fuel rods. The secondary spacer is positioned at the solid part of the respective water rod.

8. 发明授权

US09773573B2 Pressurized water reactor fuel assembly 有权
公开(公告)号：US09773573B2
公开(公告)日：2017-09-26
申请号：US14495957
申请日：2014-09-25
申请人： Westinghouse Electric Company LLC
发明人： Jin Liu
IPC分类号： G21C7/20 , G21C3/322 , G21C3/326 , G21C1/32 , G21C7/117
CPC分类号： G21C7/20 , G21C1/322 , G21C3/322 , G21C3/326 , G21C7/117 , Y02E30/32 , Y02E30/38
摘要： An elongated control rod guide thimble for a nuclear reactor having a tube-in-tube dashpot design that has circumferential slots in the dashpot walls that align with spaced openings in the guide thimble sheath. The dashpot tube has an end plug with a threaded opening extending axially therethrough which is captured by a thimble screw that extend through an opening in the bottom nozzle and sandwiches an end plug attached to the guide thimble sheath between the dashpot tube end plug and the bottom nozzle.

9. 发明申请

US20160379722A1 SYSTEMS AND METHODS FOR INCREASED STABILITY NUCLEAR FUEL CASTINGS 审中-公开
标题翻译：增加稳定性核燃料铸件的系统和方法
公开(公告)号：US20160379722A1
公开(公告)日：2016-12-29
申请号：US14754645
申请日：2015-06-29
申请人： GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
发明人： Francis T. Bolger , Wayne Marquino , Charles L. Heck , Randall H. Jacobs
IPC分类号： G21C3/322
CPC分类号： G21C3/322 , G21C3/3305 , G21C5/06 , G21C15/243 , Y02E30/38
摘要： Nuclear fuel assembly support castings direct fluid flow through nuclear fuel assemblies with relatively lower decay ratios and thus improved flow stability. The castings include an internal flow passage that is elongated to increase fluid flow inertia. The passage may be in excess of 0.3 meters and up to several meters in a straight, vertical direction that does not disrupt inertial fluid flow. Castings may omit an entry orifice and replicate any orifice-driven pressure drop with a specifically-sized flow passage that causes a similar pressure drop, or castings may use a side or bottom entry orifice at an entrance to the passage. Castings accommodate any number of fuel assemblies and other core structures including control blades, instrumentation tubes, core plates, and other core structures, such as four fuel assemblies arranged in a grid on the casting with a cruciform control element extending through a center of the casting.
摘要翻译：核燃料组件支撑铸件直接流体流过具有较低衰减比的核燃料组件，从而改善流动稳定性。铸件包括细长的内部流动通道以增加流体流动惯性。通道可能在直线垂直方向上超过0.3米，高达几米，不会破坏惯性流体流动。铸件可以省略入口孔口，并用特定尺寸的流动通道复制任何孔口驱动的压降，其导致相似的压降，或铸件可以在通道的入口处使用侧入口或底部入口。铸件容纳任何数量的燃料组件和其他核心结构，包括控制叶片，仪表管，芯板和其他芯结构，例如在铸件上排列成格栅的四个燃料组件，十字形控制元件延伸穿过铸件的中心。

10. 发明申请

US20160358674A1 METHOD AND DEVICE TO PREVENT SEVERE POWER AND FLOW OSCILLATIONS IN BOILING WATER REACTORS 审中-公开
公开(公告)号：US20160358674A1
公开(公告)日：2016-12-08
申请号：US14562636
申请日：2014-12-05
申请人： Yousef M. Farawila
发明人： Yousef M. Farawila
IPC分类号： G21C3/322 , G21C9/00 , G21C1/08
CPC分类号： G21C3/322 , G21C3/3206 , G21C3/3305 , Y02E30/31 , Y02E30/38
摘要： The present invention relates to boiling water reactors (BWR) disclosing a new method and device for preventing the flow and power oscillations from growing to severely large amplitudes thus protecting the reactor from the consequences of instabilities associated with the so-called anticipated transients without scram (ATWS). This invention introduces a new method for preventing boiling water reactor fuel damage due to the growth of unstable density wave oscillations to severely large magnitudes. The method limits the growth of the density waves by limiting the magnitude of the oscillation of the coolant mass flow rate at the inlet of the fuel bundle such that only upward flow is permitted. Further growth of the density wave beyond inlet flow reversal is thus prevented which limits the severity of the coolant flow conditions at the fuel clad surface in the entire fuel assembly such that dryout either does not occur or rewetting of the clad surface occurs every oscillation cycle such that excessive high clad temperatures that may cause its failure do not occur. A device realizing this method is comprised of a screen structure placed inside the lower tie plate of the fuel assembly. The said screen is free to move between two plates with aligned holes. The said screen is lifted upward such that the flow holes are not obstructed allowing upward flow of the coolant as required for normal operation. In the case the flow direction is reversed the hydraulic lifting force vanishes and the screen structure moves to a lower position blocking flow holes and obstructing flow in the reverse (downward) direction. This invention is particularly useful for limiting the consequences of unstable oscillation should the ability of the reactor operator to shut down the reactor power with control rod scram be lost as part of the hypothetical scenario known as anticipated transient without scram (ATWS). It is also useful to mitigate the consequences from a loss-of-coolant accident. This invention additionally functions as a debris filter to protect the cladding of the fuel rods.

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