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    MULTI-MODE HEAT REMOVAL SYSTEMS FOR NUCLEAR REACTORS AND METHODS OF USING THE SAME
    2.
    发明申请
    MULTI-MODE HEAT REMOVAL SYSTEMS FOR NUCLEAR REACTORS AND METHODS OF USING THE SAME 有权

    公开(公告)号：US20220199271A1

    公开(公告)日：2022-06-23

    申请号：US17131273

    申请日：2020-12-22

    申请人： GE-Hitachi Nuclear Energy Americas LLC

    发明人： David H. Hinds ,  Charles L. Heck

    IPC分类号： G21C15/257 ,  G21C15/25

    摘要： Piping loops can carry either forced or natural circulation coolant flow from and back to a reactor depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger that significantly cools the coolant and may even condense the coolant. The heat exchanger can drive natural circulation coolant flow, and a pump on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger in different modes. Loops may be installed directly on existing ICSs, come off of a primary loop generating electricity commercially, or be their own loop around and penetrations to the reactor. Actuation valves may isolate and actuate the system merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.

    Use of isolation condenser and/or feedwater to limit core flow, core power, and pressure in a boiling water reactor
    3.
    发明授权
    Use of isolation condenser and/or feedwater to limit core flow, core power, and pressure in a boiling water reactor 有权

    公开(公告)号：US11139087B2

    公开(公告)日：2021-10-05

    申请号：US16381147

    申请日：2019-04-11

    申请人： GE-Hitachi Nuclear Energy Americas LLC

    发明人： Charles Lee Heck ,  Michael M. Cook

    IPC分类号： G21C7/32 ,  G21C15/18 ,  G21C1/08 ,  G21D3/14 ,  G21C15/12 ,  G21D5/06 ,  G21C15/25

    摘要： A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.

    Single-Loop Nuclear Power Plant with Pressurized Coolant
    4.
    发明申请
    Single-Loop Nuclear Power Plant with Pressurized Coolant 有权

    公开(公告)号：US20210098141A1

    公开(公告)日：2021-04-01

    申请号：US16981657

    申请日：2017-12-29

    申请人： JOINT STOCK COMPANY ENGINEERING COMPANY ASE ,  JOINT STOCK COMPANY ATOMENERGOPROEKT

    发明人： Sergey Viktorovich KOROVKIN ,  Evgeniya Viktorovna TUTUNINA

    IPC分类号： G21C15/25 ,  G21C15/18

    摘要： A single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected to the throttling device and to a condenser connected to the throttling device, which device is a throttling steam generator vertically divided into a vapour zone, a high pressure zone, and a low pressure zone by horizontal sealed partitions. The high pressure zone is connected to the the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, and the low pressure zone is connected to the vapour zone by a vertical pipe which passes through the the horizontal sealed partitions and the high pressure zone. The single-loop nuclear power plant is provided with an electric motor to rotate the impeller.

    USE OF ISOLATION CONDENSER AND/OR FEEDWATER TO LIMIT CORE FLOW, CORE POWER, AND PRESSURE IN A BOILING WATER REACTOR
    5.
    发明申请
    USE OF ISOLATION CONDENSER AND/OR FEEDWATER TO LIMIT CORE FLOW, CORE POWER, AND PRESSURE IN A BOILING WATER REACTOR 审中-公开

    公开(公告)号：US20200328002A1

    公开(公告)日：2020-10-15

    申请号：US16381147

    申请日：2019-04-11

    申请人： GE-Hitachi Nuclear Energy Americas LLC

    发明人： Charles Lee Heck ,  Michael M. Cook

    IPC分类号： G21C7/32 ,  G21C1/08 ,  G21D3/14 ,  G21C15/25 ,  G21C15/18

    摘要： A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.

    METHOD AND APPARATUS FOR REPAIRING A JET PUMP SLIP JOINT
    8.
    发明申请
    METHOD AND APPARATUS FOR REPAIRING A JET PUMP SLIP JOINT 审中-公开

    公开(公告)号：US20200032936A1

    公开(公告)日：2020-01-30

    申请号：US16592103

    申请日：2019-10-03

    申请人： GE-Hitachi Nuclear Energy Americas LLC

    发明人： Lee John ANDRE ,  Jack Toshio Matsumoto

    IPC分类号： F16L23/036 ,  G21C19/20 ,  G21C15/25 ,  F04F5/10 ,  F04F5/46 ,  F04F5/54 ,  F16L55/18

    摘要： A jet pump slip joint repair assembly includes at least one clamp and a bushing configured to be inserted in a bore of a diffuser and to surround a portion of an inlet mixer. The clamp includes a gripping surface and a gripping collar. The bushing includes a generally cylindrical sidewall, the sidewall configured to surround the portion of the inlet mixer, a grooved flange on an upper surface of the sidewall, at least one cutout between adjacent portions of the grooved flange, and a groove on an inner, bottom surface of the sidewall. The assembly also includes a seal in the groove. The seal is flexible and formed of a metallic material. The seal is configured to be compressed when the at least one clamp engages the bushing.

    Sealing device for jet pump slip joints
    9.
    发明授权
    Sealing device for jet pump slip joints 有权

    公开(公告)号：US10436227B2

    公开(公告)日：2019-10-08

    申请号：US14885109

    申请日：2015-10-16

    申请人： Framatome Inc.

    发明人： Kenneth Wade Markham ,  Charles Allen Graves

    IPC分类号： F04F5/44 ,  F04F5/46 ,  F04F5/10 ,  G21C15/25

    摘要： A sealing device for a jet pump of a boiling water reactor is provided. The jet pump includes an inlet mixer and a diffuser receiving the inlet mixer at a slip joint such that an outer circumferential surface of the inlet mixer is received in an inner circumferential surface of the diffuser at the slip joint. The diffuser includes a plurality of guiding fins, each guiding fin including a radially inner surface, a radially outer surface and lateral surfaces extending radially between the inner and outer surfaces. The sealing device includes a seal configured for sealingly contacting the outer circumferential surface of the inlet mixer and a collar configured for holding the seal against the outer circumferential surface of the inlet mixer. The collar includes portions configured for being received radially between the radially inner surfaces of the guiding fins and the outer circumferential surface of the inlet mixer. The sealing device further includes a clamp configured for contacting the radially outer surfaces of the guiding fins to axially clamp the guiding fins. A method of mounting a sealing device onto a slip joint of a jet pump of a boiling water reactor is also provided.