Integral vessel isolation valve
    1.
    发明授权

    公开(公告)号:US12087456B2

    公开(公告)日:2024-09-10

    申请号:US17536404

    申请日:2021-11-29

    申请人: BWXT mPower, Inc.

    摘要: A nuclear reactor comprises a nuclear reactor core disposed in a pressure vessel. An isolation valve protects a penetration through the pressure vessel. The isolation valve comprises: a mounting flange connecting with a mating flange of the pressure vessel; a valve seat formed into the mounting flange; and a valve member movable between an open position and a closed position sealing against the valve seat. The valve member is disposed inside the mounting flange or inside the mating flange of the pressure vessel. A biasing member operatively connects to the valve member to bias the valve member towards the open position. The bias keeps the valve member in the open position except when a differential fluid pressure across the isolation valve and directed outward from the pressure vessel exceeds a threshold pressure.

    Alternating Offset U-Bend Support Arrangement

    公开(公告)号:US20210110943A1

    公开(公告)日:2021-04-15

    申请号:US17131922

    申请日:2020-12-23

    申请人: BWXT Canada Ltd.

    发明人: Kareem M.A. ALY

    摘要: Arrangement for supporting U-bend tube sections in the high heat environment of steam generators using flat bars. The invention uses a combination of thicker and thinner flat bars to impart a serpentine path to the arc of the normally curvilinear U-tubes. The support system accommodates the dilation and contraction of coolant tubes and other elements caused by the extreme and varying conditions inside a steam generator, and which can cause gaps between coolant tubes and prior art tube support bars. Bars of alternating thickness provide alternating offsets to tensionally push and support each tube on multiple sides and in multiple locations, and this tension keeps the tubes in contact with at least some flat bars on multiple sides regardless of size and shape changes. Support arrangement includes a set of fan bars, each fan bar including thick and thin flat bars projecting up and out from a collector bar.

    Alternating Offset U-Bend Support Arrangement

    公开(公告)号:US20200350085A1

    公开(公告)日:2020-11-05

    申请号:US16934479

    申请日:2020-07-21

    申请人: BWXT Canada Ltd.

    发明人: Kareem M.A. ALY

    摘要: Arrangement for supporting U-bend tube sections in the high heat environment of steam generators using flat bars. The invention uses a combination of thicker and thinner flat bars to impart a serpentine path to the arc of the normally curvilinear U-tubes. The support system accommodates the dilation and contraction of coolant tubes and other elements caused by the extreme and varying conditions inside a steam generator, and which can cause gaps between coolant tubes and prior art tube support bars. Bars of alternating thickness provide alternating offsets to tensionally push and support each tube on multiple sides and in multiple locations, and this tension keeps the tubes in contact with at least some flat bars on multiple sides regardless of size and shape changes. Support arrangement includes a set of fan bars, each fan bar including thick and thin flat bars projecting up and out from a collector bar.

    POWER CONVERSION SYSTEM FOR NUCLEAR POWER GENERATORS AND RELATED METHODS

    公开(公告)号:US20200219631A1

    公开(公告)日:2020-07-09

    申请号:US16641229

    申请日:2018-08-31

    申请人: Claudio Filippone

    发明人: Claudio Filippone

    摘要: Various exemplary embodiments of a power conversion system for converting thermal energy from a heat source to electricity are disclosed. In one exemplary embodiment, the power conversion system may include a substantially sealed chamber having an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The sealed chamber may also include an outer shroud substantially surrounding the inner shroud, such that the working fluid exiting the outlet of the inner shroud returns to the inlet of the inner shroud in a closed-loop via a return passageway formed between an external surface of the inner shroud and an internal surface of the outer shroud. The power conversion system may further include a source heat exchanger disposed in the internal passageway of the inner shroud, the source heat exchanger being configured to at least partially receive a heat transmitting element.

    ENVIRONMENTALLY ROBUST ELECTROMAGNETS AND ELECTRIC MOTORS EMPLOYING SAME FOR USE IN NUCLEAR REACTORS

    公开(公告)号:US20180278108A1

    公开(公告)日:2018-09-27

    申请号:US15989847

    申请日:2018-05-25

    摘要: An electromagnet comprises a plurality of nested freestanding electrically insulating former layers, and electrically conductive wire wrapped around the outsides of the freestanding electrically insulating former layers to define a multilayer electrical coil in which adjacent layers of the multilayer electrical coil are spaced apart by intervening freestanding electrically insulating former layers. Electrically energizing the multilayer electrical coil generates a magnetic field inside the multilayer electrical coil. In some embodiments the electrically conductive wire is bare wire not having electrical insulation. In some embodiments the former layers comprise a ceramic material. In some such embodiments the electromagnet further comprises a ferromagnetic core disposed inside the multilayer electrical coil. An electric motor employing such an electromagnet as a stator pole is also disclosed. Control rod drive mechanism (CRDM) and coolant pump embodiments are also disclosed employing such a motor, for use in a nuclear reactor.

    Nuclear reactor shroud
    8.
    发明授权

    公开(公告)号:US09773576B2

    公开(公告)日:2017-09-26

    申请号:US14771018

    申请日:2014-02-27

    申请人: SMR INVENTEC, LLC

    摘要: A nuclear reactor in one embodiment includes a cylindrical, body having an internal cavity, a nuclear fuel core, and a shroud disposed in the cavity. The shroud comprises an inner shell, an outer shell and a plurality of intermediate shells disposed between the inner and outer shells. Pluralities of annular cavities are formed between the inner and outer shells which are filled with primary coolant such as demineralized water. The coolant-filled annular cavities may be sealed at the top and bottom and provide an insulating effect to the shroud. In one embodiment, the shroud may comprise a plurality of vertically-stacked self-supported shroud segments which are coupled together.

    PASSIVE COOLING TO COLD SHUTDOWN
    9.
    发明申请

    公开(公告)号:US20170117063A1

    公开(公告)日:2017-04-27

    申请号:US14923277

    申请日:2015-10-26

    摘要: A cooling system for a reactor module includes a reactor pressure vessel that houses primary coolant and a steam generator that lowers a temperature of the reactor pressure vessel by transferring heat from the primary coolant to a secondary coolant that circulates through the steam generator. The steam generator releases at least a portion of the secondary coolant as steam. Additionally, the cooling system includes a containment vessel that at least partially surrounds the reactor vessel in a containment region. The containment region is dry during normal operation of the reactor module. A controller introduces a source of water into the containment region in response to a non-emergency shut down of the reactor module. The source of water is located external to the containment vessel, and the water is introduced into the containment region after the steam generator has initially lowered the temperature of the reactor pressure vessel in response to releasing the steam.

    OUTLET NOZZLE OF NUCLEAR REACTOR
    10.
    发明申请
    OUTLET NOZZLE OF NUCLEAR REACTOR 审中-公开
    核反应堆出口喷嘴

    公开(公告)号:US20160042818A1

    公开(公告)日:2016-02-11

    申请号:US14779913

    申请日:2013-04-23

    IPC分类号: G21C15/24

    摘要: The present invention relates to an outlet nozzle of a nuclear reactor. More specifically, in the outlet nozzle of a nuclear reactor which is provided to a reactor vessel and into which the coolant discharged from the nozzle of a structure in the reactor is introduced, the outlet nozzle of a nuclear reactor has an inclination part formed at one side of the outlet nozzle such that the inclination part is inclined at a predetermined angle from the outside end to the inside thereof. The present invention has an effect, wherein the one side of the outlet nozzle into which the coolant is introduced from the nozzle of a structure in the nuclear reactor is inclined or rounded such that an inspection robot (ASME Sec XI IWB-3512) for inspecting the presence of a defect in the coupling state of the reactor while moving along the inside surface of the reactor vessel in the reactor can move to the lower side of the reactor, and thus the volumetric inspection of the reactor by the inspection robot can be freely and continuously advanced such that the volumetric inspection can be carried out to 100% without any excluded portion for welded parts. In addition, the stability of the nuclear reactor can be more effectively verified as the volumetric inspection is carried out to 100%.

    摘要翻译: 本发明涉及核反应堆的出口喷嘴。 更具体地说,在提供给反应堆容器的核反应堆的出口喷嘴中,从反应器中的结构的喷嘴排出的冷却剂被引入其中,核反应堆的出口喷嘴具有形成在一个 使得倾斜部分从外端到内部倾斜预定的角度。 本发明具有这样的效果,其中从核反应堆中的结构的喷嘴引入冷却剂的出口喷嘴的一侧倾斜或倒圆,使得用于检查的检查机器人(ASME Sec XI IWB-3512) 在反应器内的反应器容器的内表面移动时,反应器的耦合状态的缺陷的存在可以移动到反应器的下侧,因此检查机器人的反应器的体积检查可以是自由的 并持续进行,使得体积检查可以执行到100%,没有任何排除部分的焊接部件。 另外,由于体积检测进行到100%,核反应堆的稳定性可以得到更有效的验证。