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1. 发明授权

US09200622B2 Solar-nuclear hybrid power plant 有权
标题翻译：太阳能核电混合动力发电厂
公开(公告)号：US09200622B2
公开(公告)日：2015-12-01
申请号：US14047697
申请日：2013-10-07
申请人： Babcock & Wilcox Power Generation Group, Inc.
发明人： Bartev B Sakadjian , William A Arnold , David L Kraft
IPC分类号： F03G6/00 , G21D5/00 , G21D5/16 , G21D1/00 , G21D5/10 , F22B1/00 , F22B1/12 , F22B1/16 , F22B1/02 , F01K13/00
CPC分类号： F03G6/003 , F01K13/00 , F03G6/005 , F22B1/006 , F22B1/023 , F22B1/123 , F22B1/162 , G21D1/00 , G21D1/006 , G21D5/10 , G21D5/16 , Y02E10/46 , Y02E30/40 , Y02P80/15
摘要： A solar-nuclear hybrid plant includes a nuclear energy loop, a solar energy loop, and an electrical generation loop. The three loops are closed loops. The nuclear energy loop transfers energy to the electrical generation loop through a steam generator. The solar energy loop transfers energy to either the nuclear energy loop and/or the electrical generation loop through one or more heat exchangers in the appropriate loop. This cogeneration plant has higher efficiency compared to a nuclear power plant alone.
摘要翻译：太阳能核电混合设备包括核能回路，太阳能回路和发电回路。三个循环是闭环。核能回路通过蒸汽发生器将能量传递给发电回路。太阳能回路通过适当回路中的一个或多个热交换器将能量转移到核能回路和/或发电回路中。与单独的核电厂相比，这个热电联产厂的效率更高。

2. 发明申请

US20130152588A1 METHOD AND APPARATUS FOR CONTROLLING OUTPUT OF PRESSURE SETTING SIGNAL TO AUTOMATICALLY CONTROL STEAM BYPASS CONTROL SYSTEM, AND METHOD AND APPARATUS FOR AUTOMATICALLY CONTROLLING STEAM BYPASS CONTROL SYSTEM BY USING THE PRESSURE SETTING SIGNAL 审中-公开
标题翻译：用于控制压力设定信号输出以自动控制蒸汽旁通控制系统的方法和装置，以及通过使用压力设定信号自动控制蒸汽旁通控制系统的方法和装置
公开(公告)号：US20130152588A1
公开(公告)日：2013-06-20
申请号：US13478604
申请日：2012-05-23
申请人： Myung Jun SONG , See Chae JEONG , Chan Eok PARK , Ju Han LEE , Jong Joo SOHN
发明人： Myung Jun SONG , See Chae JEONG , Chan Eok PARK , Ju Han LEE , Jong Joo SOHN
IPC分类号： G21D5/00 , F01K13/02 , G21D3/08
CPC分类号： G21D1/00 , F01K13/02 , G21D3/001 , G21D3/04 , Y02E30/40
摘要： An apparatus for controlling an output of a pressure setting signal to automatically control a steam bypass control system includes a pressure setting signal output unit for outputting a pressure setting signal according to a cold leg temperature of a reactor coolant; a first logic value output unit for outputting a first logic value that is changed according to reactor power; a second logic value output unit for outputting a second logic value that is changed according to a temperature difference between an average temperature of the reactor coolant and a reference temperature; a NAND gate circuit unit for outputting an inverse logic value according to the first and second logic values; and a first output control unit for controlling whether to output the pressure setting signal according to the inverse logic value of the NAND gate circuit unit.
摘要翻译：用于控制压力设定信号的输出以自动控制蒸汽旁路控制系统的装置包括：压力设定信号输出单元，用于根据反应堆冷却剂的冷腿温度输出压力设定信号; 第一逻辑值输出单元，用于输出根据电抗器功率而改变的第一逻辑值; 第二逻辑值输出单元，用于输出根据反应堆冷却剂的平均温度和参考温度之间的温度差而改变的第二逻辑值; NAND门电路单元，用于根据第一和第二逻辑值输出反逻辑值; 以及第一输出控制单元，用于根据与非门电路单元的反逻辑值来控制是否输出压力设定信号。

3. 发明授权

US08291704B2 Operation method of nuclear power plant 有权
标题翻译：核电厂运行方式
公开(公告)号：US08291704B2
公开(公告)日：2012-10-23
申请号：US13046329
申请日：2011-03-11
申请人： Masao Chaki , Kazuaki Kitou , Motoo Aoyama , Masaya Ootsuka , Kouji Shiina
发明人： Masao Chaki , Kazuaki Kitou , Motoo Aoyama , Masaya Ootsuka , Kouji Shiina
IPC分类号： G21D5/00 , F01K7/34
CPC分类号： G21C1/084 , G21D1/02 , G21D3/00 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.
摘要翻译：在核电站中，核反应堆的第二操作循环中的热功率在第二操作周期之前的第一操作周期内从热功率上升至少一个操作周期。在蒸汽系统中提取的蒸汽的比例相对于主蒸汽的流量被引入特定从高压汽轮机的中间点和出口抽出的给水加热器在第二操作循环，从而在第二操作循环中使得从给水加热器排出的给水温度降低1℃至40℃。

4. 发明授权

US08042498B2 Superheated steam generator 有权
标题翻译：过热蒸汽发生器
公开(公告)号：US08042498B2
公开(公告)日：2011-10-25
申请号：US11610205
申请日：2006-12-13
申请人： Kotaro Hirayama , Yoshimasa Hiramatsu , Takashi Kogin
发明人： Kotaro Hirayama , Yoshimasa Hiramatsu , Takashi Kogin
IPC分类号： F22G7/14 , F24F9/00 , G21D5/00 , F28F13/00 , H05B6/02
CPC分类号： F22G1/165 , B24B49/105
摘要： A superheated steam generator includes an introduction section for introducing saturated steam into hollow pipe members arranged as steam flow passages and acting as inductively heated elements, and a discharge section for discharging superheated steam from the flow passages, wherein a turbulence generator is disposed in each of the steam flow passages to accelerate heat transfer to the steam in the pipe members, wherein the turbulence generator is a zigzag bent member disposed in the steam flow passage, and a zigzag bending pitch of the bent member changes from rough to minute from the introduction section to the discharge section.
摘要翻译：过热蒸汽发生器包括用于将饱和蒸汽引入作为蒸汽流动通道并作为感应加热元件的中空管构件的引入部分，以及用于从流动通道排放过热蒸汽的排放部分，其中湍流发生器设置在所述蒸汽流通道加速传热到所述管件中的蒸汽，其中所述湍流发生器是设置在所述蒸汽流动通道中的曲折弯曲部件，并且所述弯曲部件的之字形弯曲间距从所述导入部分的粗略变化到分钟到排出部。

5. 发明申请

US20110162364A1 OPERATION METHOD OF NUCLEAR POWER PLANT 有权
公开(公告)号：US20110162364A1
公开(公告)日：2011-07-07
申请号：US13046329
申请日：2011-03-11
申请人： Masao Chaki , Kazuaki Kitou , Motoo Aoyama , Masaya Ootsuka , Kouji Shiina
发明人： Masao Chaki , Kazuaki Kitou , Motoo Aoyama , Masaya Ootsuka , Kouji Shiina
IPC分类号： G21D5/00 , F01K23/02
CPC分类号： G21C1/084 , G21D1/02 , G21D3/00 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

6. 发明授权

US07614233B2 Operation method of nuclear power plant 有权
标题翻译：核电厂运行方式
公开(公告)号：US07614233B2
公开(公告)日：2009-11-10
申请号：US11340643
申请日：2006-01-27
申请人： Masao Chaki , Kazuaki Kitou , Motoo Aoyama , Masaya Ootsuka , Kouji Shiina
发明人： Masao Chaki , Kazuaki Kitou , Motoo Aoyama , Masaya Ootsuka , Kouji Shiina
IPC分类号： G21D5/00
CPC分类号： G21C1/084 , G21D1/02 , G21D3/00 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.
摘要翻译：在核电站中，核反应堆的第二操作循环中的热功率在第二操作周期之前的第一操作周期内从热功率上升至少一个操作周期。在蒸汽系统中提取的蒸汽的比例相对于主蒸汽的流量被引入特定从高压汽轮机的中间点和出口抽出的给水加热器在第二操作循环，从而在第二操作循环中使得从给水加热器排出的给水温度降低1℃至40℃。

7. 发明授权

US5835548A Capsule for the containment of spent nuclear fuel and a method of manufacturing such a capsule 失效
标题翻译：用于遏制乏核燃料的胶囊和制造这种胶囊的方法
公开(公告)号：US5835548A
公开(公告)日：1998-11-10
申请号：US894697
申请日：1997-08-26
申请人： Per-Olov Lindgren , Joakim Pettersson
发明人： Per-Olov Lindgren , Joakim Pettersson
IPC分类号： G21F5/008 , C25D3/38 , G21D5/00 , G21F9/36 , G21F5/00 , G21C19/00
CPC分类号： G21D5/00 , G21Y2002/302 , G21Y2004/40
摘要： The invention relates to a capsule for the containment of spent nuclear fuel, wherein the capsule has a cylindrical part which comprises a steel cylinder tightly embraced by a copper layer whose thickness is of the same order as the thickness of the cylinder wall. The copper layer is a continuous layer applied electrolytically over the outer surface of the steel cylinder and has an homogenous grain structure. The invention also relates to a method of producing capsules for the containment of spent nuclear fuel, wherein a steel cylinder of predetermined length and diameter is placed as a cathode in an electrolytic cell containing a copper salt solution as electrolyte. An electric current whose strength is effective in precipitating copper is passed through the cell to the steel cylinder via one or more anodes, while rotating the cylinder, until a copper coating of predetermined thickness has been formed on the outer surface of the cylinder. The copper-coated cylinder is then heated to a temperature and for a period of time that will ensure that the whole of the inhomogeneous copper-grain structure formed in the electrolysis process is converted to a structure having a predetermined homogenous grain size. The coated cylinder is then cooled as rapidly as possible, so as to maintain essentially the copper-layer structure of homogenous grain size.
摘要翻译： PCT No.PCT / SE96 / 00287 Sec。 371日期：1997年8月26日 102（e）日期1997年8月26日PCT 1996年3月5日PCT公布出版物WO96 / 27884 日期1996年9月12日本发明涉及一种用于容纳乏核燃料的胶囊，其中胶囊具有圆柱形部分，该圆柱形部分包括紧密包围铜层的钢圆筒，其厚度与圆柱体的厚度相同壁。铜层是电镀在钢瓶外表面上的连续层，具有均匀的晶粒结构。本发明还涉及一种生产用于容纳废核燃料的胶囊的方法，其中将预定长度和直径的钢筒作为阴极放置在含有铜盐溶液作为电解质的电解槽中。通过一个或多个阳极，使气缸的强度有效的电流通过一个或多个阳极，同时旋转气缸，直到在气缸的外表面上形成预定厚度的铜涂层。然后将铜包覆的圆筒加热到一定温度并保持一段时间，以确保在电解过程中形成的整个不均匀的铜晶粒结构转变为具有预定均匀晶粒尺寸的结构。然后将涂覆的圆筒尽可能快地冷却，以便基本上保持均匀晶粒尺寸的铜层结构。

8. 发明授权

US5636512A Nuclear rocket feed system incorporating an auxiliary power cycle 失效
标题翻译：包含辅助动力循环的核火箭进料系统
公开(公告)号：US5636512A
公开(公告)日：1997-06-10
申请号：US324058
申请日：1994-10-14
申请人： Donald W. Culver
发明人： Donald W. Culver
IPC分类号： G21D5/02 , G21D5/00
CPC分类号： G21D5/02
摘要： A nuclear rocket engine comprising a primary feed system (4) for pumping rocket propellant from a propellant source (10) to a nuclear reactor (6) and an auxiliary feed system (60) coupled to the primary feed system. The auxiliary feed system includes a space radiator (84) for discharging excess reactor heat into space and a motorgenerator (74) for creating electricity from the excess reactor heat. A recuperator (20) operates to heat liquid propellant before it enters the reactor and to retain heat within the system. The auxiliary power system can be configured into a high thrust mode (see FIG. 1) for withdrawing heat from the engine when the reactor is operating at full power, a low thrust mode (see FIG. 2) for throttling propellant flow and radiating heat from the engine during reactor shutdown and a zero thrust mode (see FIG. 3) for cooling the nuclear reactor and generating electricity for the rocket's auxiliary power requirements for the remainder of the mission.
摘要翻译：一种核火箭发动机，其包括用于将火箭推进剂从推进剂源（10）泵送到核反应堆（6）的主进料系统（4）和耦合到主进料系统的辅助进料系统（60）。辅助进料系统包括用于将多余反应堆热量排放到空间中的空间散热器（84）和用于从多余的反应堆热量产生电力的电动发电机（74）。换热器（20）在其进入反应器之前加热液体推进剂并在系统内保持热量。辅助动力系统可以配置成高推力模式（见图1），用于当反应堆全功率运行时从发动机中排出热量，用于节流推进剂流量和辐射热的低推力模式（见图2）在反应堆关闭期间的发动机和用于冷却核反应堆的零推力模式（参见图3），并且为剩余任务中的火箭的辅助动力要求发电。

9. 发明授权

US4229942A Radiolytic dissociative gas power conversion cycles 失效
标题翻译：放射解离气体功率转换周期
公开(公告)号：US4229942A
公开(公告)日：1980-10-28
申请号：US913017
申请日：1978-06-06
申请人： Henry J. Gomberg , John G. Lewis , John E. Powers
发明人： Henry J. Gomberg , John G. Lewis , John E. Powers
IPC分类号： F01K3/18 , F02C1/04 , G21D5/00
CPC分类号： F01K3/188 , F02C1/04 , Y10S376/907
摘要： Gas and combined gas/steam power cycles in which chemical energy is stored in a gaseous working fluid by radiolytic dissociation at a temperature below the temperature of thermodynamic macroscopic dissociation, such that the dissociated portion of the working fluid exists under conditions of macroscopic thermal non-equilibrium. The dissociated fluid components are then recombined with the energy of recombination adding heat to the working fluid for extraction in the power cycle.
摘要翻译：气体和组合气体/蒸汽动力循环，其中化学能通过在低于热力学宏观解离温度的温度下的放射解离而储存在气态工作流体中，使得工作流体的解离部分存在于宏观热非离子表面活性剂的条件下，平衡。然后将解离的流体组分与重新加热的能量加热，以在工作循环中提取工作流体。

10. 发明授权

US09303629B2 System and method for power generation using a hybrid geothermal power plant including a nuclear plant 有权
标题翻译：使用包括核电厂的混合地热发电厂的发电系统和方法
公开(公告)号：US09303629B2
公开(公告)日：2016-04-05
申请号：US14145652
申请日：2013-12-31
申请人： Garry Hine
发明人： Garry Hine
IPC分类号： F03G7/00 , G21D5/00 , F03G7/04 , G21D1/00 , G21D9/00 , F22B1/02 , F24J3/08 , G21D7/00 , F28D21/00
CPC分类号： F03G7/04 , F01K13/02 , F22B1/023 , F24T10/10 , F28D2021/0054 , G21C1/07 , G21D1/00 , G21D7/00 , G21D9/00 , Y02E10/12 , Y02E30/40
摘要： A hybrid geothermal power system is discussed. The system includes a geothermal system including power plant (101) and pumping station (102) and a nuclear plant (103). Pumping station (102) is used to inject fluid from reservoir (104) through an injection well (105) into the bedrock (106) (also referred to as the hot dry rock HDR zone) and extracted via a secondary bore (extraction well) usually coupled to the power plant (101). In the present example however the injection well is linked to the extraction well (107). As fluid is injected into the bedrock a drop in temperature occurs due to heat transfer to the fluid. Nuclear plant (103) is utilized to combat this drop, the plant (103) has the fissionable components (1091, 1092, 1093) of the reactor positioned within bores (1081, 1082, 1083) within the HDR zone.
摘要翻译：讨论了混合地热发电系统。该系统包括一个包括发电厂（101）和泵站（102）和核电站（103）的地热系统。抽水站（102）用于将来自储存器（104）的流体通过注入井（105）注入基岩（也称为热干燥岩石HDR区域）中，并经由次级孔（提取井）提取，通常耦合到发电厂（101）。然而，在本示例中，注入井连接到提取井（107）。当流体被注入到基岩中时，由于向流体的传热而发生下降的温度。核设备（103）用于对抗该液滴，所述设备（103）具有位于HDR区域内的孔（1081,1082,1083）内的反应器的可裂变组分（1091,1092,1093）。

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