REACTIVITY BOOSTER-QUENCHER, AUTOMATIC POWER MODULES SEPARATOR, AND RELATED METHODS THEREOF

    公开(公告)号:US20210257118A1

    公开(公告)日:2021-08-19

    申请号:US16973132

    申请日:2019-06-10

    Abstract: A nuclear power reactor may include a plurality of power modules, each including a nuclear fuel and a power conversion system configured to convert heat generated from the nuclear fuel to electricity, where the nuclear fuel of the plurality of power modules collectively forms a reactor core. The nuclear power reactor may also include a sleeve being disposed between the plurality of power modules, where the sleeve has a first end and a second end opposite to the first end. The nuclear power reactor may further include a reactivity booster having a neutron source and a reactivity quencher having a neutron absorber. The reactivity booster may be movable between a first location adjacent the first end of the sleeve and a second location adjacent the reactor core, and the reactivity quencher may be movable between a third location adjacent the second end and the second location adjacent the reactor core.

    FLUX-SHIFTING REACTIVITY CONTROL SYSTEM

    公开(公告)号:US20210210223A1

    公开(公告)日:2021-07-08

    申请号:US17081976

    申请日:2020-10-27

    Abstract: A control assembly for a nuclear reactor includes a first reactivity control assembly having a first neutron modifying material, a second reactivity control assembly having a second neutron modifying material, and at least one drive mechanism coupled to the first neutron modifying material and the second neutron modifying material. The first neutron modifying material and the second neutron modifying material are selectively repositionable relative to a fuel region of the nuclear reactor. The at least one drive mechanism is configured to provide the first neutron modifying material and the second neutron modifying material in different directions through the fuel region thereby shifting a flux distribution within the fuel region away from the second neutron modifying material.

    REACTOR SHUTDOWN SYSTEM
    124.
    发明申请

    公开(公告)号:US20210183530A1

    公开(公告)日:2021-06-17

    申请号:US16711922

    申请日:2019-12-12

    Inventor: YASIR ARAFAT

    Abstract: A system for use in shutting down a nuclear reactor includes a housing that defines a region therein sealed from an ambient environment and a gate member disposed within the region in a manner such that the gate member segregates the region into a first compartment and a second compartment isolated from the first compartment. The gate member is formed from a material having a predetermined melting point. The system further includes a neutron absorbing material disposed within the first compartment and a dispersion mechanism disposed within the region. The dispersion mechanism structured to encourage the neutron absorbing material from the first compartment into the second compartment.

    Fuel assembly
    126.
    发明授权

    公开(公告)号:US10535435B2

    公开(公告)日:2020-01-14

    申请号:US15536581

    申请日:2015-12-04

    Applicant: Hitachi, Ltd.

    Abstract: It is possible to achieve self-support of the fuel assembly without an upper grid plate when the fuel assembly is mounted or replaced, and it is also possible to prevent the fuel assembly from floating during a reactor operation. According to the present invention, the lower portion of the lower tie plate 7 as a part of the fuel assembly 3, which is inserted into the fuel support 9, extends, and a stable member 21 is provided around the extension portion 20, and thereby it is possible to achieve the self-support of the fuel assembly without the upper grid plate. In addition, since an increase in a weight due to extension of the lower portion of the lower tie plate 7 can prevent the floating during the reactor operation, a floating preventing mechanism using the upper grid plate is not necessary. Hence, it is possible to achieve the self-support of the fuel assembly without an upper grid plate when the fuel assembly is mounted or replaced, and it is also possible to prevent the fuel assembly from floating during the reactor operation.

    POWER DISTRIBUTION PLATE FOR POWERING INTERNAL CONTROL ROD DRIVE MECHANISM (CRDM) UNITS

    公开(公告)号:US20190066855A1

    公开(公告)日:2019-02-28

    申请号:US16153289

    申请日:2018-10-05

    Abstract: A power distribution plate (PDP) sits on top of a support plate. Control rod drive mechanism (CRDM) units are mounted on top of the PDP, but the PDP is incapable of supporting the weight of the CRDM units and instead transfers the load to a support plate. The PDP has receptacles which receive cable modules each including mineral insulated (MI) cables, the MI cables being connected with the CRDM units. The PDP may further include a set of hydraulic lines underlying the cable modules and connected with the CRDM units. The cable modules in their receptacles define conduits or raceways for their MI cables and for any underlying hydraulic lines.

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