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

    IPC分类号: G21C1/14 G21C7/22 G21C15/26

    CPC分类号: G21C1/14 G21C7/22 G21C15/26

    摘要: 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.

    PASSIVE EMERGENCY FEEDWATER SYSTEM
    2.
    发明公开

    公开(公告)号:US20240312651A1

    公开(公告)日:2024-09-19

    申请号:US18359232

    申请日:2023-07-26

    IPC分类号: G21C15/18 G21C1/32 G21C15/26

    摘要: A power module assembly may include a reactor vessel containing a primary coolant and one or more inlets configured to draw a secondary coolant from the containment cooling pool in response to a loss of power and/or a loss of coolant. One or more outlets may be submerged in the containment cooling pool and may be configured to vent the secondary coolant into the containment cooling pool. A heat exchanger may be configured to remove heat from the primary coolant, wherein the heat may be removed by circulating the secondary coolant from the containment cooling pool through the heat exchanger via natural circulation.

    Integral pressurized water reactor with external steam drum
    7.
    发明授权
    Integral pressurized water reactor with external steam drum 有权
    一体式压水机与外部蒸汽鼓

    公开(公告)号:US09523496B2

    公开(公告)日:2016-12-20

    申请号:US13351940

    申请日:2012-01-17

    申请人: Billy E. Bingham

    发明人: Billy E. Bingham

    摘要: A pressurized water reactor (PWR) includes: a pressure vessel divided into an upper plenum containing primary coolant, a lower plenum containing primary coolant, and a steam generator plenum interposed between the upper plenum and the lower plenum and containing secondary coolant; a nuclear reactor core comprising fissile material disposed in the lower plenum; one or more risers arranged to convey primary coolant upward from the nuclear reactor core to the upper plenum; and a plurality of tubes passing through the steam generator plenum and arranged to convey primary coolant downward from the upper plenum to the lower plenum. A steam separator is operatively connected with the steam generator plenum to separate secondary coolant in the steam phase from secondary coolant in the water phase.

    摘要翻译: 加压水反应堆(PWR)包括:压力容器,其分为含有主要冷却剂的上部压力室,包含主要冷却剂的下部增压室和介于上部气室和下部气室之间并包含二次冷却剂的蒸汽发生器气室; 核反应堆核心,包括设置在下部增压室中的裂变材料; 一个或多个立管布置成将一次冷却剂从核反应堆堆芯向上输送到上部通风室; 并且多个管通过蒸汽发生器压力室并且被布置成将主冷却剂从上部压力室向下输送到下部充气室。 蒸汽分离器与蒸汽发生器压力室可操作地连接,以将蒸汽相中的二级冷却剂与水相中的二级冷却剂分开。

    CHIMNEY ASSEMBLY OF A REACTOR PRESSURE VESSEL AND METHOD OF STORING THE SAME DURING A NUCLEAR REACTOR OUTAGE
    8.
    发明申请
    CHIMNEY ASSEMBLY OF A REACTOR PRESSURE VESSEL AND METHOD OF STORING THE SAME DURING A NUCLEAR REACTOR OUTAGE 有权
    反应器压力容器的烟囱组件及其在核反应堆出口期间的储存方法

    公开(公告)号:US20160042820A1

    公开(公告)日:2016-02-11

    申请号:US14453118

    申请日:2014-08-06

    IPC分类号: G21C19/32 G21C1/32

    摘要: A method of storing a chimney assembly of a reactor pressure vessel during a nuclear reactor outage may include detaching a chimney barrel with upper chimney partitions therein from a top guide assembly of the reactor pressure vessel. A height of the upper chimney partitions is less than a height of the chimney barrel so as to leave a plenum region in a top section of the chimney barrel. The top guide assembly includes lower chimney partitions therein. The lower chimney partitions are removed from the top guide assembly and inserted into the plenum region of the chimney barrel so as to be on the upper chimney partitions. As a result, the chimney assembly can be stored in a relatively compact form during a reactor outage. The chimney assembly may be a combination of at least the chimney barrel, the upper chimney partitions, and the lower chimney partitions.

    摘要翻译: 在核反应堆中断期间存储反应堆压力容器的烟囱组件的方法可以包括从反应堆压力容器的顶部引导组件将具有上部烟囱分隔件的烟囱筒分离。 上烟囱隔板的高度小于烟囱筒的高度,以便在烟囱筒的顶部部分中留下增压室。 顶部导向组件包括其中的下部烟囱分隔件。 下部烟囱分隔件从顶部引导组件移除并插入到烟囱筒的增压室区域中,以便在上部烟囱分隔壁上。 结果,烟囱组件可以在反应堆中断期间以相对紧凑的形式存储。 烟囱组件可以是至少烟囱筒,上部烟囱分隔件和下部烟囱分隔件的组合。

    Passive containment air cooling for nuclear power plants
    9.
    发明授权
    Passive containment air cooling for nuclear power plants 有权
    核电厂的被动遏制空气冷却

    公开(公告)号:US09177675B2

    公开(公告)日:2015-11-03

    申请号:US13444967

    申请日:2012-04-12

    IPC分类号: G21C15/14 G21C15/18 G21C15/26

    摘要: A passive containment air cooling system for a nuclear power plant that enhances air flow over a metal containment that houses the reactor system to improve heat transfer out of the containment. The heat transfer is improved by employing swirl vanes to mix the air as it rises over the walls of the containment due to natural circulation and a vortex engine proximate an exit along the cooling air path to increase the quantity of air drawn along the containment.

    摘要翻译: 一种用于核电厂的无源遏制空气冷却系统,其增强容纳反应堆系统的金属容器上的空气流动,以改善从密封件传热的热量。 通过采用旋流叶片来混合空气,由于其自​​然循环而在空气的壁上上升,并且沿着冷却空气路径靠近出口的涡流发动机来增加热传递,从而增加沿着容纳物吸入的空气量。

    FEEDWATER TEMPERATURE CONTROL METHODS AND SYSTEMS
    10.
    发明申请
    FEEDWATER TEMPERATURE CONTROL METHODS AND SYSTEMS 失效
    进水温度控制方法和系统

    公开(公告)号:US20090016479A1

    公开(公告)日:2009-01-15

    申请号:US11777377

    申请日:2007-07-13

    IPC分类号: G21C7/00

    摘要: In various embodiments, a system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) is provided. In various embodiments, the system includes a heating subsystem for heating feedwater flowing into an annulus of a NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system includes a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus. By increasing the temperature of the feedwater flowing into the annulus, the temperature of the recirculation water is increased above the predetermined recirculation water operating temperature causing a reduction in the power level generated by the NCBWR core.

    摘要翻译: 在各种实施例中,提供了一种用于控制自然循环沸水核反应堆(NCBWR)的功率水平的系统。 在各种实施例中,该系统包括加热子系统,用于加热流入NCBWR的环形空气中的给水以增加流过芯的再循环水的温度高于预定再循环水运行温度。 另外,该系统包括温度传感器,该温度传感器可操作以感测流入环形空气的给水温度。 温度传感器通信地连接到温度控制器,温度控制器可操作以命令加热子系统将流入环形空气的给水温度升高到高于流入环空的给水的预定工作温度的要求温度。 通过增加供给水流入环空的温度,再循环水的温度升高到超过预定再循环水的工作温度,导致由NCBWR芯产生的功率水平的降低。