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公开(公告)号：US20240300061A1
公开(公告)日：2024-09-12
申请号：US18254694
申请日：2021-11-12
IPC分类号： B23P19/06 , G21C13/024 , G21C13/073 , G21C19/10 , G21C19/20
CPC分类号： B23P19/067 , G21C13/024 , G21C13/073 , G21C19/10 , G21C19/207
摘要： Disclosed is a method of tensioning/detensioning closure studs of a nuclear reactor vessel. The closure studs are spaced about a circumference of the reactor vessel so as to attach an integrated head package (IHP) of the reactor vessel to a body of the reactor vessel. The method comprises supporting a first stud tensioner device on a trolley, moving the trolley across a movement surface from a stored position to a deployment position adjacent the reactor vessel, engaging the first stud tensioner device with one or more of the closure studs, and operating the first stud tensioner device to tension/detension the one or more closure studs.
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公开(公告)号：US20240194362A1
公开(公告)日：2024-06-13
申请号：US18554424
申请日：2022-04-14
发明人： Daniel ROBERTSON
摘要： A lift head for a reactor pressure vessel comprising a lift head which can be coupled and removed to a reactor pressure vessel head, and radiation shielding. The radiation shielding is connectable to the lift head such that the lift head and the radiation shield encase the reactor pressure vessel head and any head package contents removed from a reactor pressure vessel with the reactor pressure vessel head. The radiation shield may be of a clam shell construction. The lift head may be provided with a mechanism for fastening and unfastening the bolts connecting the reactor pressure vessel head to the reactor pressure vessel. The lift head may be provided with monitoring equipment to monitor the core internals.
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公开(公告)号：US20230420148A1
公开(公告)日：2023-12-28
申请号：US18039128
申请日：2021-11-12
IPC分类号： G21C13/073 , G21C19/20 , G21C19/32
CPC分类号： G21C13/073 , G21C19/207 , G21C19/32
摘要： Disclosed is a nuclear power generation system comprising a reactor vessel comprising a body defining a cavity housing a reactor core, and an integrated head package having a closure head for closing an opening to the cavity. The system also comprises a containment structure having a working floor surrounding and substantially vertically aligned with the opening to the cavity.
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公开(公告)号：US20230317307A1
公开(公告)日：2023-10-05
申请号：US18016508
申请日：2021-07-14
发明人： Adam SPINKS , Daniel ROBERTSON , Stephen CALVERT , Matthew MORRIS , Euan SHARP , Gerard HALLIDAY
摘要： The present disclosure provides a lifting device for lifting a closure head assembly from a reactor vessel body in a nuclear power generation system. The lifting device comprises at least one lifting element having an engagement surface configured to engage an underside surface of the closure head assembly. The at least one lifting element is axially adjustable in height between a retracted position in which its axial height is such that the closure head assembly seals against the body of the reactor vessel and an extended position in which its axial height is such that the closure head assembly is raised above the body of the reactor vessel.
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公开(公告)号：US20240021331A1
公开(公告)日：2024-01-18
申请号：US18254110
申请日：2021-11-12
IPC分类号： G21C19/20 , G21C19/10 , G21C13/073 , G21C17/108
CPC分类号： G21C19/207 , G21C19/10 , G21C13/073 , G21C17/108
摘要： 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.
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公开(公告)号：US20230420150A1
公开(公告)日：2023-12-28
申请号：US18254016
申请日：2021-11-12
CPC分类号： G21C19/207 , G21C19/10 , G21C19/32
摘要： 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.
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公开(公告)号：US20230162874A1
公开(公告)日：2023-05-25
申请号：US17913356
申请日：2021-03-26
发明人： Daniel ROBERTSON , Brett LONGSTAFFE
摘要： A reactor control system for a nuclear reactor, the reactor control system comprising: one or more hollow tubes comprising neutron absorbing material, each having a first end and a second end; a pump connected to the first end of each hollow tube and operable to control the amount of a first fluid within the hollow tube, the first fluid comprising a neutron moderator, wherein: the pump is controlled based on a level of reactivity in the nuclear reactor, and the second end of the hollow tubes is in fluid communication with a second fluid, the second fluid having a neutron moderating capacity lower than 10% of that of the first fluid.
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公开(公告)号：US20220230768A1
公开(公告)日：2022-07-21
申请号：US17614165
申请日：2020-05-13
发明人： Daniel ROBERTSON
IPC分类号： G21C13/024 , G21C15/18
摘要： A pressure-containing silo for one or more components on a primary coolant circuit of a nuclear reactor having nuclear fuel assemblies cooled by coolant circulating the primary coolant circuit, the silo defining a release space which, in a loss-of-coolant accident releasing the pressurised coolant water from the one or more components therein, receives and contains the released water and steam, at increasing pressure, formed therefrom; wherein the silo is formed from plural, substantially identical, stacked and joined modular units, each having: a concrete body, a metal liner which lines a surface of the concrete body, and which, when the units are stacked and joined, is sealed edge-to-edge with metal liners of neighbouring units forming an inward-facing, pressure-containing skin surrounding the release space, and plural conduits which, when the units are stacked, align with the conduits of neighbouring units to receive elongate tensioning members for post-stressing the concrete of the bodies.
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