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81. 发明授权

US3771497A Vapor generator control 失效
标题翻译：蒸汽发生器控制
公开(公告)号：US3771497A
公开(公告)日：1973-11-13
申请号：US3771497D
申请日：1972-04-26
申请人： BABCOCK & WILCOX CO
发明人： SPRAGUE T , SCHLICTING J , MCDONALD B
IPC分类号： F22B1/06 , F22B1/02 , F22B1/16 , F22B35/00 , F22B37/38 , F22B37/42 , F28F27/00 , G21D5/12
CPC分类号： F22B35/004 , F22B1/026 , G21D5/12
摘要： A vapor generating system comprising a pressure vessel wherein secondary liquid is vaporized through indirect heat exchange with a hot primary fluid and including a control arrangement whereby thermal shock stresses in the vessel are limited by controlled preheating of secondary liquid being fed thereto.
摘要翻译：一种蒸汽发生系统，包括压力容器，其中通过与热的初级流体进行间接热交换而使二次液体蒸发，并且包括控制装置，由此通过被供给的二次液体的受控预热来限制容器中的热冲击应力。

82. 发明授权

US3369971A Apparatus for controlling a nuclear reactor plant 失效
标题翻译：用于控制核反应堆的装置
公开(公告)号：US3369971A
公开(公告)日：1968-02-20
申请号：US40700464
申请日：1964-10-28
申请人： SULZER AG
发明人： JAKOB KAGI
IPC分类号： F22B1/08 , F22B35/00 , G03D15/02 , G21D3/08 , G21D3/12
CPC分类号： G21D3/12 , F22B1/08 , F22B35/004 , G03D15/022 , G21D3/08 , Y02E30/40

83. 发明授权

US3349003A Method of heating working medium in the heat exchanger of a nuclear reactor installation 失效
标题翻译：在核反应堆设备的热交换器中加热工作介质的方法
公开(公告)号：US3349003A
公开(公告)日：1967-10-24
申请号：US47828365
申请日：1965-08-09
申请人： SULZER AG
发明人： JAKOB KAGI
IPC分类号： F22B1/08 , F22B35/00 , G03D15/02 , G21D3/08 , G21D3/12
CPC分类号： G21D3/12 , F22B1/08 , F22B35/004 , G03D15/022 , G21D3/08 , Y02E30/40

84. 发明授权

US3127877A Once-through boiler and method of operating the boiler 失效
标题翻译：一次锅炉和锅炉操作方法
公开(公告)号：US3127877A
公开(公告)日：1964-04-07
申请号：US4312460
申请日：1960-07-15
申请人： SULZER AG
发明人： PAUL PROFOS
IPC分类号： E05B63/04 , F22B1/08 , F22B1/18 , F22B35/00 , F22B35/10 , G21D3/08 , G21D5/14
CPC分类号： G21D5/14 , E05B63/048 , F22B1/08 , F22B1/1823 , F22B35/004 , F22B35/101 , F22B35/102 , G21D3/08 , Y02E30/40

85. 发明授权

US11996208B2 Controlling a power output of a nuclear reactor without using control rods 有权
公开(公告)号：US11996208B2
公开(公告)日：2024-05-28
申请号：US17693685
申请日：2022-03-14
申请人： NuScale Power, LLC
发明人： Allyson Callaway , Ben Bristol , Kenneth Rooks , Larry Linik
IPC分类号： G21C7/12 , G21C7/22 , G21C9/033 , G21D3/14 , G21D3/16 , G21D3/18 , F22B35/00 , G21C1/02 , G21C7/08 , G21C7/24 , G21C9/02 , G21C13/02 , G21D1/00 , G21D3/02 , G21D5/08
CPC分类号： G21C7/12 , G21C7/22 , G21C9/033 , G21D3/14 , G21D3/16 , G21D3/18 , F22B35/004 , G21C1/028 , G21C7/08 , G21C7/24 , G21C9/02 , G21C13/022 , G21D1/006 , G21D3/02 , G21D5/08
摘要： A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction. A representative nuclear power system further includes a riser positioned above there actor core and a primary coolant flow path that extends from a bottom portion of the reactor vessel, through the reactor core, and through an annulus between the riser and the reactor vessel. A primary coolant circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to a power generation system configured to generate electric power. The nuclear power system further includes a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.

86. 发明公开

US20230142980A1 COOLANT CLEANUP AND HEAT-SINKING SYSTEMS AND METHODS OF OPERATING THE SAME 审中-公开
公开(公告)号：US20230142980A1
公开(公告)日：2023-05-11
申请号：US18092580
申请日：2023-01-03
申请人： GE-Hitachi Nuclear Energy Americas LLC
发明人： Derek Bass , Christer N. Dahlgren
IPC分类号： G21C19/307 , F22B35/00 , G21D1/00 , G21C15/243
CPC分类号： G21C19/307 , F22B35/004 , G21D1/006 , G21C15/243
摘要： Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.

87. 发明授权

US09945814B2 Total integrated tube analysis 有权
公开(公告)号：US09945814B2
公开(公告)日：2018-04-17
申请号：US14800076
申请日：2015-07-15
申请人： WESTINGHOUSE ELECTRIC COMPANY, LLC.
发明人： Qui V. Le , Stephen J. Beehner
IPC分类号： G01B3/44 , G01B3/52 , G01N27/90 , F22B1/02 , B24B49/10 , F22B35/00
CPC分类号： G01N27/9046 , B24B49/105 , F22B1/023 , F22B35/004 , G01N27/9073
摘要： The invention relates to improved systems and methods for inspecting the tubes of a steam generator of a nuclear reactor that involves modeling the steam generator, comparing signals of a tube from an eddy current sensor with aspects of the model to determine whether further analysis is required, employing primary and secondary analysis processes, and producing a combined report of the primary and secondary analysis results.

88. 发明申请

US20160189807A1 STEAM GENERATOR LEVEL CONTROL SYSTEM AND METHOD OF PREVENTING OSCILLATION OF STEAM GENERATOR LEVEL 审中-公开
标题翻译：蒸汽发生器水平控制系统及其防止蒸汽发生器水平振荡的方法
公开(公告)号：US20160189807A1
公开(公告)日：2016-06-30
申请号：US14981407
申请日：2015-12-28
申请人： KEPCO ENGINEERING & CONSTRUCTION COMPANY, INC.
发明人： In Ho SONG , Myung Jun SONG , See Chae JEONG , Ju Han LEE , Shin Whan Kim , Eung Seo Kim
IPC分类号： G21C7/32 , G21C7/36 , G21D3/00
CPC分类号： G21D3/001 , F22B35/004 , F22B37/46 , F22D5/30 , F22D5/32 , G21D3/04 , Y02E30/40
摘要： Provided are a method and system for improving control of a steam generator level for preventing oscillation of the steam generator level in a nuclear power plant. In order to prevent oscillation of a steam generator level and resultant shutdown of a nuclear reactor, which may be caused when a high-level priority control function is frequently and repeatedly turned on/off as the steam generator level is excessively increased, by improving a feedwater control system in the nuclear power plant, a proportional integral control value may be controlled to be reduced, and thus, output while a certain condition is met after a high-level priority mode is deactivated or a signal instructing to enter the high-level priority control mode may be controlled not to be output.
摘要翻译：提供了一种用于改善蒸汽发生器水平的控制以防止核电站中的蒸汽发生器水平的振荡的方法和系统。为了防止当蒸汽发生器水平过度增加时高水平优先控制功能频繁且重复打开/关闭时可能引起的蒸汽发生器水平的振荡和核反应堆的关闭，通过改进核电厂的给水控制系统，可以将比例积分控制值控制为降低，从而在高电平优先模式被禁用或者指示进入高电平的信号之后满足一定条件时输出可以控制优先级控制模式不被输出。

89. 发明申请

US20120040299A1 DYNAMIC MATRIX CONTROL OF STEAM TEMPERATURE WITH PREVENTION OF SATURATED STEAM ENTRY INTO SUPERHEATER 有权
标题翻译：蒸汽温度的动态矩阵控制，防止蒸汽进入超级加热器
公开(公告)号：US20120040299A1
公开(公告)日：2012-02-16
申请号：US13022324
申请日：2011-02-07
申请人： Robert A. Beveridge , Richard J. Whalen, JR.
发明人： Robert A. Beveridge , Richard J. Whalen, JR.
IPC分类号： F22B37/00
CPC分类号： F22B35/18 , F01K13/02 , F22B35/004
摘要： A technique of controlling a steam generating boiler system using dynamic matrix control includes preventing saturated steam from entering a superheater section. A dynamic matrix control block uses a rate of change of a disturbance variable, a current output steam temperature, and an output steam setpoint as inputs to generate a control signal. A prevention block modifies the control signal based on a saturatec temperature and an intermediate steam temperature. In some embodiments, the control signal is modified based on a threshold and/or an adjustable function g(x). The modified control signal is used to control a field device that, at least in part, affects the intermediate steam and output steam of the boiler system. In some embodiments, the prevention block is included in the dynamic matrix control block.
摘要翻译：使用动态矩阵控制来控制蒸汽发生锅炉系统的技术包括防止饱和蒸汽进入过热器部分。动态矩阵控制块使用干扰变量，当前输出蒸汽温度和输出蒸汽设定点的变化率作为输入来产生控制信号。预防块基于饱和温度和中间蒸汽温度来修改控制信号。在一些实施例中，基于阈值和/或可调整函数g（x）来修改控制信号。改进的控制信号用于控制至少部分地影响锅炉系统的中间蒸汽和输出蒸汽的现场设备。在一些实施例中，预防块被包括在动态矩阵控制块中。

90. 发明授权

US06886502B1 Method for controlling steam generators 有权
标题翻译：蒸汽发生器控制方法
公开(公告)号：US06886502B1
公开(公告)日：2005-05-03
申请号：US10874666
申请日：2004-06-23
申请人： Jagannathan Seenu Srinivasan
发明人： Jagannathan Seenu Srinivasan
IPC分类号： F22B35/00 , F22D5/30
CPC分类号： F22B35/004
摘要： A method of controlling the feedwater flow to the secondary side of a steam generator in a pressurized water nuclear reactor monitors various process variables such as the feedwater and the steam flows and pressures around the secondary side of the steam generator and then generates process signals based upon the process variables. An error signal based upon selected process signals is generated. The error signal is filtered by a deadband filter network for generating a control signal with a deadband. The control signal with a deadband is sent to a proportional-integral controller for generating a demand signal. The demand signal is then sent to an operator such as feedwater valve positioner or a feedwater pump speed controller for controlling the feedwater flow into the steam generator.
摘要翻译：控制在加压水核反应堆中的蒸汽发生器的二次侧的给水流的方法监测各种过程变量，例如给水和蒸汽流以及蒸汽发生器的次级侧周围的压力，然后基于过程变量。产生基于所选择的处理信号的误差信号。误差信号由死区滤波器网络滤波，用于产生具有死区的控制信号。具有死区的控制信号被发送到比例积分控制器以产生需求信号。然后将需求信号发送给诸如给水阀定位器或给水泵速度控制器的操作者，用于控制进入蒸汽发生器的给水流。

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