DRILLHOLE NUCLEAR REACTOR
    44.
    发明公开

    公开(公告)号:US20240339231A1

    公开(公告)日:2024-10-10

    申请号:US18744364

    申请日:2024-06-14

    Abstract: A nuclear reactor system includes a first drillhole extending from a terranean surface through one or more subterranean formations; a reactor core positioned in the first drillhole, and including at least one nuclear fuel element; a second drillhole extending from the terranean surface through the one or more subterranean formations and separated from the first drillhole by a portion of a rock formation; a heat exchanger positioned in the second drillhole in thermal communication with the reactor core through the portion of the rock formation; and a coolant system thermally coupled to the heat exchanger and configured to transport a fluid coolant between the heat exchanger and the terranean surface.

    A LOW PRESSURE WATER REACTOR AND A METHOD FOR CONTROLLING A LOW PRESSURE WATER REACTOR

    公开(公告)号:US20240339230A1

    公开(公告)日:2024-10-10

    申请号:US18294810

    申请日:2022-08-02

    CPC classification number: G21C1/14 G21C7/22 G21C15/26

    Abstract: A low pressure water reactor (LPWR) and a method for controlling a LPWR; the LPWR comprises a reactor vessel with an internal cavity comprising a primary coolant, a riser tube, and a core located below ground level with 6-15 bars atmosphere pressure; a steam drum connected to the riser tube at ground level at a pressure of 1-10 bars absolute; a water storage tank to store borated water; a passive injection system injecting the borated water from the water storage tank into the vessel; and low pressure steam turbines generating power at 1-10 bars atmosphere. The vessel heats water up to temperature and the riser tube converts the heated water to steam, delivered to the turbine(s). The conversion creates a difference in a primary coolant density that initiates a density-driven natural circulation of the primary coolant in the riser tube, downcomer, steam drum and core.

    Safety control circuit for a neutronic reactor
    49.
    发明授权
    Safety control circuit for a neutronic reactor 失效
    用于中子反应堆的安全控制电路

    公开(公告)号:US06728328B1

    公开(公告)日:2004-04-27

    申请号:US03429712

    申请日:1954-05-13

    Abstract: A neutronic reactor comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the reactor comprising a safety device and a regulating device, a safety device including means defining a vertical channel extending into the reactor from an aperture in the upper surface of the reactor, a rod containing neutron-absorbing materials slidably disposed within the channel, means for maintaining the safety rod in a withdrawn position relative to the active portion of the reactor including means for releasing said rod on actuation thereof, a hopper mounted above the active portion of the reactor having a door disposed at the bottom of the hopper opening into the vertical channel, a plurality of bodies of neutron-absorbing materials disposed within the hopper, and means responsive to the failure of the safety rod on actuation thereof to enter the active portion of the reactor for opening the door in the hopper.

    Abstract translation: 一种中子反应器,包括含有可由热能中子裂变的材料的活性部分,用于控制反应器内的中子链反应的装置,该反应器包括安全装置和调节装置,安全装置包括限定从反应器中延伸进入反应器的垂直通道的装置 在反应器的上表面中的孔,包含可滑动地设置在通道内的中子吸收材料的杆,用于将安全杆相对于反应器的有效部分保持在撤回位置的装置,包括用于在致动时释放所述杆的装置, 安装在反应器的有效部分上方的料斗,其具有设置在料斗开口的底部进入垂直通道的门,设置在料斗内的多个中子吸收材料体,以及响应于安全杆故障的装置 在其启动时进入反应器的活动部分,以打开料斗中的门。

    Variable speed pump for use in nuclear reactor
    50.
    发明授权
    Variable speed pump for use in nuclear reactor 失效
    用于核反应堆的变速泵

    公开(公告)号:US6160863A

    公开(公告)日:2000-12-12

    申请号:US108118

    申请日:1998-07-01

    Inventor: Philip H. Hepner

    CPC classification number: G21C15/243 G21C7/22 Y02E30/39

    Abstract: A nuclear reactor coolant system includes a primary coolant circuit connected to a secondary coolant circuit. A desired amount of coolant is bled from the primary circuit to the secondary circuit for purification and controlling chemical composition of the coolant. Variable speed charging pumps are provided in the secondary circuit to pump coolant back into the primary circuit at variable pressures and flow rates. A pressurizer level control system is also disclosed for controlling pump speeds.

    Abstract translation: 核反应堆冷却剂系统包括连接到二次冷却剂回路的主冷却剂回路。 所需量的冷却剂从初级回路排放到次级回路,用于净化和控制冷却剂的化学成分。 在二次回路中提供变速充气泵,以可变的压力和流量将冷却剂泵回主回路。 还公开了一种用于控制泵速度的加压器液位控制系统。

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