NUCLEAR REACTOR AND FUEL
    53.
    发明公开

    公开(公告)号:US20240153654A1

    公开(公告)日:2024-05-09

    申请号:US18550166

    申请日:2022-03-14

    申请人: Oklo Inc.

    发明人: Jacob DeWitte

    摘要: A commercial nuclear fuel system includes: a vessel that defines an inner volume; a reactor core positioned within the inner volume; and a plurality of fuel pins disposed in the reactor core, each of the plurality of fuel pins comprising at least one hydride fuel element positioned in a cladding. The at least one hydride fuel element is enriched to twenty percent or less of fissile material. The fissile material comprises one or more of uranium-233, uranium-235, or plutonium-239. The fuel pins are positioned in a lattice within the reactor core. The vessel comprises a first vessel, and a second vessel is positioned within the first vessel and surrounds the plurality of fuel pins. At least one reflector is positioned within the first vessel and surrounds the plurality of fuel pins. A shielding assembly is positioned between the reflector and the first vessel.

    Control rod drive mechanism with separate latch and drive coils

    公开(公告)号:US11309095B2

    公开(公告)日:2022-04-19

    申请号:US16831201

    申请日:2020-03-26

    IPC分类号: G21C7/12 G21C7/14 G21C9/02

    摘要: A control rod drive mechanism for use in a nuclear reactor including a reactor core disposed in a pressure vessel, including a control rod configured for insertion into the reactor core, a lead screw, the control rod being secured to the bottom end of the lead screw, a drive mechanism including a torque tube having a top end and a bottom end, a pair of segment arms that are pivotably mounted to the torque tube, a pair of roller nuts, each roller nut being rotatably secured to the bottom end of a respective segment arm, and a drive motor including a stator and a rotor secured to the top end of the torque tube that includes a plurality of permanent magnets embedded therein, wherein the stator defines a central bore in which the rotor is disposed, and a latch coil assembly including a latch coil, wherein the latch coil assembly defines a central bore in which the top ends of the segment arms are disposed radially-inwardly of the latch coil.

    Control rod drive mechanism and reactor control system

    公开(公告)号:US11164682B1

    公开(公告)日:2021-11-02

    申请号:US17356844

    申请日:2021-06-24

    IPC分类号: G21C7/14 G21C9/02 G21C7/12

    摘要: This disclosure relates to reactor control, and more particularly to a control rod drive mechanism and a reactor control system. The control rod drive mechanism includes a lifting-lowering assembly, a mounting assembly and a release assembly. The mounting assembly is configured to mount a control rod. The lifting-lowering assembly includes a fixing component, a scissor-type lifting-lowering mechanism and a lifting-lowering component. An end of the scissor-type lifting-lowering mechanism is connected to the fixing component, and the other end is connected to the lifting-lowering component. The scissor-type lifting-lowering mechanism is configured to drive the lifting-lowering component to move close to or away from the fixing component. The release assembly is movably arranged on the lifting-lowering component, and is detachably connected to the mounting assembly. The release assembly is configured to move relative to the lifting-lowering component when power is off to release the mounting assembly.

    Nuclear reactor module with a cooling chamber for a drive motor of a control rod drive mechanism

    公开(公告)号:US11114209B2

    公开(公告)日:2021-09-07

    申请号:US16226298

    申请日:2018-12-19

    发明人: Tamas Liszkai

    摘要: In some embodiments, a nuclear reactor vessel comprises a containment vessel for a reactor pressure vessel (RPV); a control rod drive mechanism (CRDM) located in the containment vessel, the CRDM including drive motors configured to move control rods into and out of a nuclear reactor core located in the RPV; and a partition extending across a portion of the containment vessel configured to retain the drive motors in a separate fluid-tight barrier region within the containment vessel. Other embodiments may be disclosed and/or claimed.

    Fail-safe control rod drive system for nuclear reactor

    公开(公告)号:US11094421B2

    公开(公告)日:2021-08-17

    申请号:US16744144

    申请日:2020-01-15

    申请人: SMR Inventec, LLC

    IPC分类号: G21C7/14 G21C9/02 G21C7/12

    摘要: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

    Fail-safe control rod drive system for nuclear reactor

    公开(公告)号:US10573419B2

    公开(公告)日:2020-02-25

    申请号:US15288436

    申请日:2016-10-07

    申请人: SMR Inventec, LLC

    IPC分类号: G21C7/14 G21C7/12 G21C9/02

    摘要: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

    CONTROL ROD DRIVE MECHANISM WITH HEAT PIPE COOLING

    公开(公告)号:US20200027588A1

    公开(公告)日:2020-01-23

    申请号:US16229554

    申请日:2018-12-21

    IPC分类号: G21C7/14 H02K9/20

    摘要: A cooling system for a nuclear reactor control rod drive mechanism (CRDM) includes an evaporation section located within or next to the CRDM and a condensation section fluidly coupled to the evaporation section. The cooling system may include a set of heat fins that extend up from drive coils in the CRDM and heat pipes that extend through the drive coils and heat fins. A fluid evaporates while in the evaporation section of the heat pipes from heat generated by the CRDM and moves out of the evaporation section into the condensation section in the heat fins. The fluid cools and condensates while in the condensation section, recirculating back into the evaporation section. This passive natural circulation cooling system reduces or eliminates the number of water hoses, piping, and other water pumping equipment typically used for cooling CRDM, or the requirement for air cooling, increasing nuclear reactor reliability and simplifying nuclear reactor operation and maintenance.

    Base plate mounted core components for reliable rod assembly and rapid field disassembly

    公开(公告)号:US10510451B2

    公开(公告)日:2019-12-17

    申请号:US15789409

    申请日:2017-10-20

    摘要: A mounting assembly that has no threaded connections. A rod with pins or machined features radially extending from a distal end is configured to rotate until the pins align with grooves in a hole through a base plate. The rod is inserted through the hole until the pins are through an opposite surface of the base plate, compressing spring components on the rod. Then the rod is rotated until the pins are aligned with slots that partially extend through the second side of the base plate and the pins become seated in the slots. To remove the rod a tool that engages an articulated feature on the distal end of the rod is installed. The tool rotates the rod until the pins are disengaged from the slots, aligned with the through grooves and passed through the base plate.