SYSTEM AND METHOD FOR MODELING A NUCLEAR REACTOR

    公开(公告)号:WO2018157157A3

    公开(公告)日:2018-08-30

    申请号:PCT/US2018/020027

    申请日:2018-02-27

    Abstract: A system is provided that determines optimal movements of fuel assemblies in a nuclear reactor, such as a traveling wave reactor (TWR). Such a system may be capable of modeling core operations and fuel moves in parallel to determine optimal fuel cycle moves responsive to one or more constraints, including, but not limited to core criticality and location of a deflagration wave within an operating reactor core. According to one embodiment, the optimal solution may be determined using a branch search to simulate possible fuel moves.

    AUTOMATIC HYDROPNEUMATIC ACTUATION DEVICE
    3.
    发明申请
    AUTOMATIC HYDROPNEUMATIC ACTUATION DEVICE 审中-公开
    自动水力驱动装置

    公开(公告)号:WO2016109798A1

    公开(公告)日:2016-07-07

    申请号:PCT/US2015/068285

    申请日:2015-12-31

    Abstract: A control assembly for a nuclear reactor having a pump includes a duct having an inner volume and defining a coolant flow path, a plug fixed to the duct, a rod disposed within the inner volume and having a rod end that is configured to engage a neutron modifying material, a first piston disposed within the inner volume, slidably coupled to the duct, and coupled to the rod, and a biasing member coupled to the rod and the first piston. The biasing member is positioned to apply a biasing force that repositions the first piston, the rod, and the neutron modifying material in response to a loss of pump flow without scram condition.

    Abstract translation: 用于具有泵的核反应堆的控制组件包括具有内部容积并限定冷却剂流动路径的管道,固定到管道的塞子,设置在内部容积内的杆,并且具有构造成接合中子的杆端 设置在所述内部容积内的第一活塞,可滑动地联接到所述管道并且联接到所述杆,以及联接到所述杆和所述第一活塞的偏置构件。 偏置构件被定位成施加偏置力,该偏置力响应于泵流量的损失而不使用冲击状态来重新定位第一活塞,杆和中子修饰材料。

    SYSTEM AND METHOD FOR MODELING A NUCLEAR REACTOR

    公开(公告)号:WO2018157157A4

    公开(公告)日:2018-08-30

    申请号:PCT/US2018/020027

    申请日:2018-02-27

    Abstract: A system is provided that determines optimal movements of fuel assemblies in a nuclear reactor, such as a traveling wave reactor (TWR). Such a system may be capable of modeling core operations and fuel moves in parallel to determine optimal fuel cycle moves responsive to one or more constraints, including, but not limited to core criticality and location of a deflagration wave within an operating reactor core. According to one embodiment, the optimal solution may be determined using a branch search to simulate possible fuel moves.

    SYSTEM AND METHOD FOR MODELING A NUCLEAR REACTOR

    公开(公告)号:WO2018157157A2

    公开(公告)日:2018-08-30

    申请号:PCT/US2018/020027

    申请日:2018-02-27

    Abstract: A system is provided that determines optimal movements of fuel assemblies in a nuclear reactor, such as a traveling wave reactor (TWR). Such a system may be capable of modeling core operations and fuel moves in parallel to determine optimal fuel cycle moves responsive to one or more constraints, including, but not limited to core criticality and location of a deflagration wave within an operating reactor core. According to one embodiment, the optimal solution may be determined using a branch search to simulate possible fuel moves.

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