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1.发明公开公开(公告)号：US20240296966A1
公开(公告)日：2024-09-05
申请号：US18444473
申请日：2024-02-16
申请人： Fred Donald Lang
发明人： Fred Donald Lang
IPC分类号： G21C17/032 , G21C7/32 , G21C17/022
CPC分类号： G21C17/032 , G21C7/32 , G21C17/022
摘要： This invention relates to the monitoring and diagnosing of nuclear power plants for its thermal performance using the NCV Method. Its applicability comprises any nuclear reactor such as used for research producing a useful output. Its greatest applicability lies with conventional Pressurized Water Reactor and Boiling Water Reactor nuclear plants generating an electric power. Its teachings of treating fission as an inertial process, a phenomena which is self-contained following incident neutron capture, allows the determination of an absolute neutron flux. This process is best treated by Second Law principles producing a total fission exergy. This invention also applies to the design of fusion thermal systems regards the determination of its Second Law viability and absolute plasma flux.
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公开(公告)号：US20240266083A1
公开(公告)日：2024-08-08
申请号：US18437013
申请日：2024-02-08
申请人： SMR Inventec, LLC
IPC分类号： G21C15/243 , G21C7/32 , G21C13/073 , G21C15/26 , G21D1/00
CPC分类号： G21C15/243 , G21C7/32 , G21C15/26 , G21C13/073 , G21D1/00 , G21D1/006 , Y02E30/30
摘要： A nuclear steam supply system having a start-up sub-system for heating a primary coolant. The nuclear steam supply system comprises a reactor vessel with core comprising nuclear fuel, and steam generating vessel fluidly coupled to the reactor vessel. A primary coolant loop formed within the reactor vessel and the steam generating vessel circulates primary coolant through the loop. A steam supply start-up sub-system is fluidly coupled to the primary coolant loop. The start-up sub-system is configured and operable to: (1) extract and receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant back into the primary coolant loop.
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公开(公告)号：US11955248B2
公开(公告)日：2024-04-09
申请号：US17466109
申请日：2021-09-03
发明人： Charles Lee Heck , Michael M. Cook
摘要： A method and apparatus of limiting power of a boiling water nuclear reactor system includes a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud surrounding the reactor core, a downcomer region disposed between an inner surface of the reactor pressure vessel and the core shroud, a steam line connected to an upper end of the reactor pressure vessel and a condenser system that receives steam from the reactor pressure vessel. A portion of the condenser system condensate is returned to the reactor pressure vessel of the boiling water reactor inside the core barrel above the core rather than into the downcomer. Returning the condensate in this way increases the effectiveness of an isolation condenser system or if the condensate is a portion of the feedwater from the main condenser it provides an effective means to regulate core flow and core power.
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公开(公告)号：US11862354B2
公开(公告)日：2024-01-02
申请号：US18044479
申请日：2021-09-01
申请人： Ian Richard Scott
发明人： Ian Richard Scott
摘要： A passive nuclear reactor control device. The passive nuclear reactor control device comprises a sealed chamber, which comprises a reservoir and a tube in fluid communication with the reservoir. A molten salt is within the sealed chamber, the molten salt being a eutectic mixture of a monovalent metal halide, and a fluoride or chloride of one or more lanthanides and/or a fluoride or chloride of hafnium. A gas is within the sealed chamber, and the gas does not react with the molten salt.
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公开(公告)号：US20140226776A1
公开(公告)日：2014-08-14
申请号：US14257608
申请日：2014-04-21
IPC分类号： G21C7/32
CPC分类号： G21C7/32 , G21C15/26 , G21C17/032 , G21Y2002/201 , G21Y2004/30 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： A system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) may include a heating subsystem for heating feedwater flowing into an annulus of the NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system may include 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： 用于控制自然循环沸水核反应堆（NCBWR）的功率水平的系统可以包括加热子系统，用于加热流入NCBWR的环形空气中的给水，以增加在预定的循环水运行之上流过芯的再循环水的温度 温度。 另外，系统可以包括温度传感器，其可操作以感测流入环空的给水的温度。 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提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。
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6.发明授权Control system and method for pressurized water reactor (PWR) and PWR systems including same 有权包括压水堆（PWR）和压水堆系统的控制系统和方法公开(公告)号：US08781057B2
公开(公告)日：2014-07-15
申请号：US12970067
申请日：2010-12-16
申请人： John D. Malloy , Billy E. Bingham
发明人： John D. Malloy , Billy E. Bingham
摘要： A pressurized water reactor (PWR) comprises a pressure vessel, a reactor core disposed in the pressure vessel, an integral or external pressurizer, primary coolant disposed in the pressure vessel and heated by operation of the reactor core, and a steam generator disposed in the pressure vessel and configured to convert secondary coolant in the form of feedwater into steam by heat transfer from the primary coolant heated by operation of the reactor core to secondary coolant in the steam generator. A controller is configured to perform a PWR control method including the operations of (i) adjusting one or more parameters of the PWR and (ii) adjusting a pressurizer water level setpoint based on a predicted direction and magnitude of change of a pressurizer water level of the PWR predicted to result from the adjusting (i).
摘要翻译： 加压水反应器（PWR）包括压力容器，设置在压力容器中的反应堆芯，整体或外部加压器，设置在压力容器中并通过反应堆芯的操作加热的一次冷却剂和设置在压力容器中的蒸汽发生器 压力容器并且被配置为通过从通过反应堆芯的操作加热的一次冷却剂通过蒸汽发生器中的二次冷却剂的热传递将给水形式的二次冷却剂转换成蒸汽。 控制器被配置为执行PWR控制方法，其包括以下操作：（i）调整PWR的一个或多个参数，以及（ii）基于预测的加压器水位变化的方向和大小来调整加压器水位设定点 PWR预测是由调整（i）引起的。
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7.发明申请CONTROL SYSTEM AND METHOD FOR PRESSURIZED WATER REACTOR (PWR) AND PWR SYSTEMS INCLUDING SAME 有权用于加压水反应器（PWR）的控制系统和方法以及包括其的PWR系统公开(公告)号：US20120155594A1
公开(公告)日：2012-06-21
申请号：US12970067
申请日：2010-12-16
申请人： John D. Malloy , Billy E. Bingham
发明人： John D. Malloy , Billy E. Bingham
IPC分类号： G21C7/32
摘要： A pressurized water reactor (PWR) comprises a pressure vessel, a reactor core disposed in the pressure vessel, an integral or external pressurizer, primary coolant disposed in the pressure vessel and heated by operation of the reactor core, and a steam generator disposed in the pressure vessel and configured to convert secondary coolant in the form of feedwater into steam by heat transfer from the primary coolant heated by operation of the reactor core to secondary coolant in the steam generator. A controller is configured to perform a PWR control method including the operations of (i) adjusting one or more parameters of the PWR and (ii) adjusting a pressurizer water level setpoint based on a predicted direction and magnitude of change of a pressurizer water level of the PWR predicted to result from the adjusting (i).
摘要翻译： 加压水反应器（PWR）包括压力容器，设置在压力容器中的反应堆芯，整体或外部加压器，设置在压力容器中并通过反应堆芯的操作加热的一次冷却剂和设置在压力容器中的蒸汽发生器 压力容器并且被配置为通过从通过反应堆芯的操作加热的一次冷却剂通过蒸汽发生器中的二次冷却剂的热传递将给水形式的二次冷却剂转换成蒸汽。 控制器被配置为执行PWR控制方法，其包括以下操作：（i）调整PWR的一个或多个参数，以及（ii）基于预测的加压器水位的改变的方向和大小来调整加压器水位设定点 PWR预测是由调整（i）引起的。
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8.发明授权Reactor-turbine control for low steam pressure operation in a pressurized water reactor 失效反应器 - 涡轮机控制在压力水反应堆中的低蒸汽压力操作
公开(公告)号：US4000037A
公开(公告)日：1976-12-28
申请号：US419746
申请日：1973-11-28
CPC分类号： G21D3/16 , G21C7/00 , G21C7/32 , G21D3/00 , G21Y2002/201 , G21Y2004/302 , G21Y2004/40 , Y02E30/32 , Y02E30/39
摘要： A control system for a pressurized water reactor power plant. The control system comprises temperature sensing means having flow interruption means connected thereto. The temperature sensing means monitors the temperature levels within the reactor element and sends a predetermined signal to the flow interruption means upon a predetermined change in reactor temperature. The flow interruption means is disposed within an associated steam turbine loop including a steam generator element which transforms secondary water into steam to act as motive fluid within the turbine loop. The flow interruption means initiate one or more flow interruption activities which either produce an increased temperature differential between the secondary water and the steam produced therefrom or increase the rate of flow of steam within the associated steam turbine loop. Utilization of the control system permits extensive operation of the reactor element past the end of the normal fuel cycle life. In addition, the control system provides improved reactor load follow capability.
摘要翻译： 压水堆发电厂控制系统。 控制系统包括具有连接到其上的流动中断装置的温度检测装置。 温度检测装置监测反应堆元件内的温度水平，并且在反应器温度的预定变化时将预定信号发送到流量中断装置。 流动中断装置设置在相关联的汽轮机回路中，包括蒸汽发生器元件，该蒸汽发生器元件将二次水转化为蒸汽以在涡轮机回路内充当动力流体。 流动中断装置启动一个或多个流动中断活动，其中产生二次水和由此产生的蒸汽之间的温度差异增加，或增加相关汽轮机回路内蒸汽的流量。 控制系统的使用允许反应器元件在正常燃料循环寿命结束之后的大量操作。 此外，控制系统提供改进的反应堆负载跟随能力。
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9.发明授权Water cooled nuclear reactor with improved core and reflector recirculation system 失效具有改进的核心和反射器再循环系统的水冷核反应堆
公开(公告)号：US3280004A
公开(公告)日：1966-10-18
申请号：US34088564
申请日：1964-01-29
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公开(公告)号：US20180226162A1
公开(公告)日：2018-08-09
申请号：US15945612
申请日：2018-04-04
申请人： NuScale Power, LLC.
发明人： Tamas LISZKAI , Seth Cadell , Alex Kruskamp , Matthew Mallet
CPC分类号： G21C15/12 , F22B1/023 , G21C1/32 , G21C1/322 , G21C7/32 , G21C13/02 , G21C15/16 , G21D1/006 , Y02E30/40
摘要： A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.
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