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    Method for replacing nuclear reactor core
    2.
    发明授权
    Method for replacing nuclear reactor core 有权

    公开(公告)号：US12148539B2

    公开(公告)日：2024-11-19

    申请号：US17398777

    申请日：2021-08-10

    Applicant: Radiant Industries, Incorporated

    Inventor： Doug Bernauer ,  Armand Eliassen

    IPC: G21C19/10 ,  G21C19/20 ,  G21C1/12 ,  G21C5/06 ,  G21C5/10 ,  G21C19/18 ,  G21C19/19

    Abstract: A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums.

    NUCLEAR REACTOR CORE LOADING AND OPERATION STRATEGIES
    4.
    发明公开
    NUCLEAR REACTOR CORE LOADING AND OPERATION STRATEGIES 审中-公开

    公开(公告)号：US20240312647A1

    公开(公告)日：2024-09-19

    申请号：US18228642

    申请日：2023-07-31

    Applicant: GLOBAL NUCLEAR FUEL - AMERICAS, LLC

    Inventor： Gregory J. Pearson ,  Atul A. Karve

    IPC: G21C3/326 ,  G21C19/20

    CPC classification number: G21C3/326 ,  G21C19/205 ,  Y02E30/30

    Abstract: Cores include different types of control cells in different numbers and positions. A periphery of the core just inside the perimeter may have higher reactivity fuel in outer control cells, and lower reactivity cells may be placed in an inner core inside the inner ring. Cores can include about half fresh fuel positioned in higher proportions in the inner ring and away from inner control cells. Cores are compatible with multiple core control cell setups, including BWRs, ESBWRs, ABWRs, etc. Cores can be loaded during conventional outages. Cores can be operated with control elements in only the inner ring control cells for reactivity adjustment. Control elements in outer control cells need be moved only at sequence exchanges. Near end of cycle, reactivity in the core may be controlled with inner control cells alone, and control elements in outer control cells can be fully withdrawn.

    SERIAL HIGH-TEMPERATURE GAS-COOLED REACTOR NUCLEAR SYSTEMS AND OPERATING METHODS THEREOF
    5.
    发明公开
    SERIAL HIGH-TEMPERATURE GAS-COOLED REACTOR NUCLEAR SYSTEMS AND OPERATING METHODS THEREOF 审中-公开

    公开(公告)号：US20240127975A1

    公开(公告)日：2024-04-18

    申请号：US18484494

    申请日：2023-10-11

    Applicant: Huaneng Nuclear Energy Technology Research Institute Co. Ltd.

    Inventor： Tao ZHANG ,  Xingtian ZHANG ,  Huaquan LV ,  Wenbin WEI ,  Yong LUO ,  Jilan ZHANG ,  Miaomiao WANG

    IPC: G21C15/253 ,  G21C1/07 ,  G21C19/20

    CPC classification number: G21C15/253 ,  G21C1/07 ,  G21C19/202

    Abstract: The invention discloses a serial high-temperature gas-cooled reactor nuclear energy system and an operating method thereof. The serial high-temperature gas-cooled reactor nuclear energy system includes a plurality of high-temperature gas-cooled reactors and a serial gas-cooled reactor. The high-temperature gas-cooled reactor includes a first reactor pressure vessel comprising a first reaction chamber for accommodating the first fuel element; a second reactor pressure vessel comprising a second reaction chamber interconnected with the first reaction chamber, allowing the first spent fuel in the first reaction chamber to enter the second reaction chamber. The system of the present invention allows the spent fuel discharged from the high-temperature gas-cooled reactor to be directly reused as fuel for the serial gas-cooled reactor, thereby improving the utilization rate of nuclear fuel and reducing the cost of gas-cooled reactors, which is conducive to the promotion of industrialized application of high-temperature gas-cooled reactors.

    INTEGRATED HEAD PACKAGE
    6.
    发明公开
    INTEGRATED HEAD PACKAGE 审中-公开

    公开(公告)号：US20240021331A1

    公开(公告)日：2024-01-18

    申请号：US18254110

    申请日：2021-11-12

    Applicant: Rolls-Royce SMR Limited

    Inventor： Daniel ROBERTSON ,  Euan SHARP ,  Gerard HALLIDAY ,  Stephen CALVERT ,  Matthew MORRIS

    IPC: G21C19/20 ,  G21C19/10 ,  G21C13/073 ,  G21C17/108

    CPC classification number: G21C19/207 ,  G21C19/10 ,  G21C13/073 ,  G21C17/108

    Abstract: The present disclosure provides an integrated head package for a nuclear power generation system, the integrated head package comprising a closure head, and a control rod drive mechanism housed within a shroud. The control rod drive mechanism comprises at least one drive rod extending through the closure head and having a coupling element for releasably coupling to a control rod assembly within a reactor core. The at least one drive rod is movable to a maintenance/refuelling position in which the at least one drive rod is uncoupled from the control rod assembly and at least partially retracted into the integrated head package. The integrated head package further comprises at least one engagement feature for securing the at least one drive rod in the maintenance/refuelling position.

    NUCLEAR REACTOR WITH AN AXIALLY STRATIFIED FUEL BED
    7.
    发明公开
    NUCLEAR REACTOR WITH AN AXIALLY STRATIFIED FUEL BED 审中-公开

    公开(公告)号：US20240013936A1

    公开(公告)日：2024-01-11

    申请号：US17811400

    申请日：2022-07-08

    Applicant: X-Energy, LLC

    Inventor： Howard Kim ,  Daniel Brown

    IPC: G21C1/07 ,  G21C19/20 ,  G21C17/112

    CPC classification number: G21C1/07 ,  G21C19/202 ,  G21C17/112

    Abstract: A nuclear reactor has an axially stratified fuel bed. The reactor features a reactor shell having a base, a top having an exhaust outlet, and an axis. The axially stratified fuel bed is within the reactor shell, and includes:



    a first zone configured to operate at a first temperature T1, the first zone comprising a plurality of first fuel particles, each first fuel particle comprising a first radioactive ceramic core and a first ceramic seal coating; and
    a second zone configured to operate at a second temperature T2, where T2>T1, the second zone comprising a plurality of second fuel particles, each second fuel particle comprising a second radioactive ceramic core and a second ceramic seal coating. A coolant fluid flow path carries a coolant fluid from the base of the reactor to the exhaust outlet, along a flow path passing sequentially through the first zone and the second zone. The first ceramic seal coating has greater stability at T1 than at T2, and the second ceramic seal coating has greater stability at T2 than the first ceramic seal coating.

    INTERNALS LIFTING DEVICE
    8.
    发明公开
    INTERNALS LIFTING DEVICE 审中-公开

    公开(公告)号：US20230420150A1

    公开(公告)日：2023-12-28

    申请号：US18254016

    申请日：2021-11-12

    Applicant: Rolls-Royce SMR Limited

    Inventor： Daniel ROBERTSON ,  Euan SHARP ,  Gerard HALLIDAY ,  Stephen CALVET ,  Matthew MORRIS

    IPC: G21C19/20 ,  G21C19/10 ,  G21C19/32

    CPC classification number: G21C19/207 ,  G21C19/10 ,  G21C19/32

    Abstract: The present disclosure provides a lifting and transport device for lifting upper internals from a reactor core of a nuclear power generation system in a deployment location and transporting them to a storage location. The lifting/transport device comprises a device body formed of radioactive shielding material, the device body defining a storage chamber having an open base. The device further comprises a movable sealing plate formed of radioactive shielding material, the sealing plate being movable between an open position in which the storage chamber is open and a closed position in which the storage chamber is sealed. There is also a lifting system mounted within the storage chamber having a lifting rig for releasable connection to the upper internals and configured to raise the upper internals to within the storage chamber when the device is in the deployment location and the plate is in the open position. The device comprises wheels for guiding movement of the lifting/transport device between the deployment location and the storage location.

    NUCLEAR REFUELLING DEVICE
    10.
    发明公开
    NUCLEAR REFUELLING DEVICE 审中-公开

    公开(公告)号：US20230298775A1

    公开(公告)日：2023-09-21

    申请号：US18016615

    申请日：2021-07-14

    Applicant: ROLLS-ROYCE PLC

    Inventor： Daniel ROBERTSON ,  Euan SHARP ,  Gerard HALLIDAY ,  Stephen CALVERT ,  Matthew MORRIS

    IPC: G21C19/20 ,  G21C19/10 ,  G21C19/32

    CPC classification number: G21C19/20 ,  G21C19/10 ,  G21C19/32

    Abstract: The present disclosure provides a refuelling device for lifting a fuel rod assembly from a reactor core of a nuclear power generation system in a deployment location and transporting it to a storage location. The refuelling device comprises a device body having an open base and defining a chamber for housing a coolant. A sealing plate is movable between an open position in which the chamber is open and a closed position in which the chamber is sealed. The device further comprises a shielding element formed of radioactive shielding material and moveably mounted within the chamber. It has a storage cavity having an open lower end, the shielding element being movable between a retracted position in which it is fully contained within the chamber and an extended position in which it extends from the chamber through the open base of the device body. The device further comprises a rod lifting system having a rod connector for releasable connection to the fuel rod assembly and configured to raise the fuel rod assembly to within the storage cavity when the device is in the deployment location, the sealing plate is in the open position and the shielding element is in its extended position.

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