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1. 发明申请

US20180068748A1 Magnetic Field Plasma Confinement for Compact Fusion Power 有权
公开(公告)号：US20180068748A1
公开(公告)日：2018-03-08
申请号：US14242939
申请日：2014-04-02
申请人： Lockheed Martin Corporation
发明人： Thomas John McGuire
IPC分类号： G21B1/05 , G21B1/13
CPC分类号： G21B1/05 , G21B1/057 , G21B1/13 , G21Y2002/303 , G21Y2004/30 , H05H1/14 , Y02E30/126
摘要： In one embodiment, a fusion reactor includes two internal magnetic coils suspended within an enclosure, a center magnetic coil coaxial with the two internal magnetic coils and located proximate to a midpoint of the enclosure, a plurality of encapsulating magnetic coils coaxial with the internal magnetic coils, and two mirror magnetic coil coaxial with the internal magnetic coils. The encapsulating magnetic coils preserve the magnetohydrodynamic (MHD) stability of the fusion reactor by maintaining a magnetic wall that prevents plasma within the enclosure from expanding.

2. 发明授权

US09881702B2 Hydraulic control unit and method of shutting down a nuclear reactor using the same 有权
公开(公告)号：US09881702B2
公开(公告)日：2018-01-30
申请号：US14565819
申请日：2014-12-10
申请人： Kenneth Allan Morgan , Filemon Tecson Cabrera , Randy Morris Brown
发明人： Kenneth Allan Morgan , Filemon Tecson Cabrera , Randy Morris Brown
IPC分类号： G21C7/16 , G21C9/02 , G21C7/36 , G21D3/06 , F15B1/02 , F15B1/10 , G21C7/08
CPC分类号： G21C7/16 , F15B1/022 , F15B1/103 , F15B2201/205 , F15B2201/3153 , G21C7/08 , G21C7/36 , G21C9/02 , G21D3/06 , G21Y2002/40 , G21Y2004/30 , Y02E30/40
摘要： A method of shutting down a nuclear reactor may include compressing a scram gas that is in fluid communication with a scram accumulator. The scram accumulator defines a chamber therein and contains bellows within the chamber. The bellows are configured to hold a scram liquid in isolation of the scram gas. The scram gas exerts a compressive force on the bellows in a form of stored energy. The method may additionally include releasing the stored energy in response to a scram signal such that the scram gas expands into the chamber of the scram accumulator to compress the bellows and expel the scram liquid from the scram accumulator to insert control rods into a core of the nuclear reactor.

3. 发明申请

US20170186503A1 COMPRESSED AIR, UTILITY-SCALE, NON-POLLUTING ENERGY STORAGE AND NUCLEAR REACTOR EMERGENCY COOLING SYSTEM USING THERMAL POWER PLANT WASTE HEAT 审中-公开
公开(公告)号：US20170186503A1
公开(公告)日：2017-06-29
申请号：US15242350
申请日：2016-08-19
申请人： Willard Harvey Wattenburg
发明人： Willard Harvey Wattenburg
IPC分类号： G21C15/18 , F01D25/08 , G21C15/253 , F01D15/10
CPC分类号： G21C15/182 , F01D15/10 , F01D25/08 , F05D2220/70 , F05D2260/213 , G21C15/18 , G21C15/253 , G21C2015/185 , G21D1/02 , G21D3/04 , G21Y2002/50 , G21Y2004/30 , Y02E30/40
摘要： Modifications to power plants for moderating climate warming and increasing safety combine a large compressed air energy storage (CAES) system with a thermal power plant such that free power plant waste heat replaces natural gas used at existing and planned CAES facilities. The system allows higher percentages of wind and solar energy on existing grids. The compressed air in a companion CAES can cool a nuclear reactor during an emergency. Also an inexpensive, add-on, external, Emergency Core Cooling System (ECCS) can cool a nuclear reactor after shutdown, even when all internal cooling water circulation has been disabled. All embodiments are installed outside the plant where they will not be damaged in the event of a plant accident. Both systems use environmentally friendly compressed air energy storage in new ways, and can be built and installed quickly around the world at existing plants using only proven infrastructure.

4. 发明授权

US09685244B2 Active zone of lead-cooled fast reactor 有权
公开(公告)号：US09685244B2
公开(公告)日：2017-06-20
申请号：US15112578
申请日：2014-11-27
申请人： STATE ATOMIC ENERGY CORPORATION “ROSATOM” ON BEHALF OF THE RUSSIAN FEDERATION
发明人： Viktor Nikolaevich Leonov , Aleksandr Viktorovich Lopatkin , Elena Aleksandrovna Rodina , Yuriy Vasilievich Chernobrovkin
IPC分类号： G21C1/02 , G21C3/04 , G21C3/42 , G21C5/14 , G21C3/58
CPC分类号： G21C3/04 , G21C1/02 , G21C1/022 , G21C3/42 , G21C3/58 , G21C5/14 , G21C2003/045 , G21Y2002/50 , G21Y2004/10 , G21Y2004/30 , Y02E30/34 , Y02E30/35 , Y02E30/38
摘要： An active zone includes a homogeneous uranium-plutonium nitride fuel, the mass fraction of which is a minimum 0.305, and consists of central, intermediate and peripheral parts which form fuel assemblies comprising fuel elements with geometrically identical shells but differing heights. The radial distribution of the fuel across the volume of the active zone has a stepped shape. The radius of the central part is from 0.4 to 0.5 of the effective active zone radius, while the height of the fuel column in the fuel elements in the central part is from 0.5 to 0.8 of the height of the fuel column in the peripheral part. The heights of the fuel columns forming a stepped intermediate part for diameters ranging from 0.5 to 0.85 of the effective active zone diameter are within the range from 0.55 to 0.9 of the height of the fuel column in the peripheral part.

5. 发明申请

US20170025192A1 METHOD FOR FABRICATION OF FULLY CERAMIC MICROENCAPSULATED NUCLEAR FUEL 审中-公开
标题翻译：全陶瓷微核燃料燃烧方法
公开(公告)号：US20170025192A1
公开(公告)日：2017-01-26
申请号：US15218245
申请日：2016-07-25
申请人： Ultra Safe Nuclear Corporation
发明人： Lance Lewis SNEAD
IPC分类号： G21C3/04 , G21C3/07 , C04B35/63 , C04B37/00 , C04B35/565 , C04B35/64
CPC分类号： G21C3/04 , C04B35/5158 , C04B35/565 , C04B2235/3217 , C04B2235/3225 , C04B2235/3227 , C04B2235/52 , C04B2235/5445 , C04B2235/5454 , C04B2235/602 , C04B2235/6562 , C04B2235/666 , C04B2235/77 , C04B2235/79 , C04B2235/94 , G21C3/07 , G21C3/20 , G21C3/62 , G21C2003/045 , G21Y2002/50 , G21Y2004/30 , Y02E30/38
摘要： Currently, the commercial fuel of choice, UO2-zircaloy, is economical due to an established and simple fabrication process. However, the alternatives to the UO2-zircaloy that may improve on system safety are sought. The fully ceramic microencapsulated (FCM) fuel system that is potentially inherently safe fuel and is an improvement on the UO2-zircaloy system is prohibitively expensive because of the known methods to produce it. Disclosed herein is a new production route and fixturing that produces identical or superior FCM fuel consistent with mass production by providing a plurality of tristructural-isotropic fuel particles; mixing the plurality of tristructural-isotropic fuel particles with ceramic powder to form a mixture; placing the mixture in a die; and applying a current to the die so as to sinter the mixture by direct current sintering into a fuel element.
摘要翻译：目前，由于建立和简单的制造工艺，选择的商业燃料UO2-ZrO2O是经济的。然而，寻求可能改善系统安全性的替代氧化锆氧化锆。具有潜在固有安全性的燃料的完全陶瓷微胶囊化（FCM）燃料系统是由于已知的生产方法而非常昂贵的，因为其对氧化锆氧化锆氧化锆系统的改进是昂贵的。本文公开了一种新的生产路线和夹具，其通过提供多个三组分各向同性燃料颗粒而产生与大量生产一致的相同或优异的FCM燃料; 将多个三组分各向同性燃料颗粒与陶瓷粉末混合以形成混合物; 将混合物置于模具中; 以及向所述管芯施加电流，以通过直接烧结将所述混合物烧结成燃料元件。

6. 发明申请

US20160379726A1 MODELING FOR FUEL ELEMENT DEFORMATION 审中-公开
标题翻译：燃料元素变形建模
公开(公告)号：US20160379726A1
公开(公告)日：2016-12-29
申请号：US14605831
申请日：2015-01-26
申请人： TerraPower, LLC
发明人： Micah Hackett , Ryan Latta , Samuel J. Miller , Gary Povirk , Mark R. Werner , Cheng Xu
IPC分类号： G21D3/00 , G21C3/04
CPC分类号： G21D3/001 , G21C3/02 , G21C3/04 , G21C3/06 , G21C2003/045 , G21D2003/004 , G21Y2004/30 , Y02E30/40
摘要： A computerized system for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof includes a processor coupled to memory, the memory configuring the processor to execute a fuel element analysis and an output configured to communicate data that describes the thermo-mechanical performance of the fuel element and fuel design based on the fuel element performance analysis. The processor is configured to estimate the mechanical behavior of a fuel by creating separate variables for the open and closed porosity components, conducting a routine for the open and closed porosity components that processes the current state of the fuel and updates the current state and forces of each of the open and closed porosity components, and combining the updates for the current state and forces according to a weighting; and estimate the creep and swelling behavior of a cladding.
摘要翻译：用于对反应堆燃料元件和燃料设计进行建模以确定其热机械性能的计算机化系统包括耦合到存储器的处理器，配置处理器以执行燃料元件分析的存储器和被配置为传达描述热机械的数据的输出基于燃油元件性能分析的燃油元件性能和燃油设计。处理器被配置为通过为开放和闭合的孔隙率分量创建单独的变量来估计燃料的机械行为，为开放和闭合的孔隙组件执行程序，处理燃料的当前状态并更新当前状态和每个打开和闭合的孔隙组件，并且根据加权组合当前状态和力的更新; 并估计包层的蠕变和膨胀行为。

7. 发明申请

US20160351280A1 NUCLEAR GRADE AIR ACCUMULATING, ISOLATING, INDICATING AND VENTING DEVICE 审中-公开
标题翻译：核级空气累积，隔离，指示和通风装置
公开(公告)号：US20160351280A1
公开(公告)日：2016-12-01
申请号：US15115676
申请日：2014-01-31
申请人： Nuccorp, Inc.
发明人： Willie Turner WOOD, JR. , Scott J. ECHERER
IPC分类号： G21C19/28 , G21C17/022 , G21D1/02
CPC分类号： G21C19/28 , F16K24/044 , F16K37/0016 , G21C17/022 , G21D1/02 , G21Y2002/50 , G21Y2004/30 , Y02E30/40
摘要： A device for isolating, accumulating, indicating and venting gas in a fluid system pipe includes a coupling affixed to a sys tem pipe. The coupling includes an isolation valve. A standpipe is attached to the coupling. The standpipe holds a float trapped between a flow retaining orifice and a closed upper end save for an angled hole therein that allows gas to flow around the float. An indicator exterior to the pipe indicates the float's level in the standpipe regardless of system pressure changes. A vent valve attached above the standpipe allows controlled ventilation of the gas flowing from the system pipe through the standpipe and through the vent valve. Accumulation of gas from the system pipe lowers the float in the standpipe, at which point the user vents the gas, causing the float to rise with the rising fluid level.
摘要翻译：用于在流体系统管道中隔离，积聚，指示和排出气体的装置包括固定在系统管道上的联接件。联轴器包括隔离阀。立管连接在联轴器上。立管保持在流动保持孔和闭合的上端之间的浮子，除了其中的倾斜孔之外，还允许气体围绕浮子流动。管道外部的指示器表示立管中的浮子水平，无论系统压力如何变化。连接在立管上方的排气阀允许从系统管道流过立管并通过排气阀的气体的受控通风。系统管道中的气体积聚会降低立管中的浮子，此时用户排出气体，导致浮子随液面上升而上升。

8. 发明申请

US20160233000A1 CASK TRANSPORT ASSEMBLY 审中-公开
标题翻译： CASK运输总成
公开(公告)号：US20160233000A1
公开(公告)日：2016-08-11
申请号：US15131760
申请日：2016-04-18
申请人： Konecranes Global Corporation
发明人： Steve Coogan , Michael Waedekin , Joseph A. Yustus
IPC分类号： G21F5/14
CPC分类号： G21F5/14 , B66C1/66 , B66C15/00 , B66C19/005 , B66C19/02 , B66D1/26 , B66D3/06 , G21Y2002/303 , G21Y2002/305 , G21Y2004/30
摘要： A cask transport system includes a support assembly including a plurality of wheels and a support frame coupled to and supported by the wheels. The cask transport system also includes a tower disposed above the support assembly, the tower including a base portion and a tower frame coupled to the base portion, the tower frame movable relative to the base portion. The cask transport system also includes an upper beam assembly coupled to the tower frame, and a bottom block assembly coupled to the upper beam assembly, the bottom block assembly movable relative to the upper beam assembly.
摘要翻译：一个桶运输系统包括支撑组件，该支撑组件包括多个轮子和一个联接到车轮上并由其支撑的支撑框架。所述桶运输系统还包括设置在所述支撑组件上方的塔架，所述塔架包括底座部分和联接到所述基座部分的塔架，所述塔架框架可相对于所述基座部分移动。所述桶运输系统还包括联接到所述塔框架的上梁组件和联接到所述上梁组件的底块组件，所述底块组件相对于所述上梁组件可移动。

9. 发明授权

US09343187B2 Compact nuclear reactor with integral steam generator 有权
标题翻译：紧凑型核反应堆集成蒸汽发生器
公开(公告)号：US09343187B2
公开(公告)日：2016-05-17
申请号：US12891317
申请日：2010-09-27
申请人： Mathew W. Ales , Robert T. Fortino , Nick Idvorian
发明人： Mathew W. Ales , Robert T. Fortino , Nick Idvorian
IPC分类号： G21C15/00 , G21C1/32
CPC分类号： G21C1/322 , F22B1/026 , G21C1/32 , G21C1/326 , G21C19/28 , G21D1/006 , G21Y2004/30 , Y02E30/40
摘要： In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.
摘要翻译：在说明性实施例中，加压水核反应堆（PWR）包括压力容器（12,14,16），设置在压力容器中的核反应堆芯（10）和设置在压力容器内的垂直取向的中空中心提升管（36）核反应堆核心在压力容器内。设置在压力容器中的直通蒸汽发生器（OTSG）（30）包括布置在由中央提升管和压力容器限定的环形容积中的垂直管（32）。 OTSG还包括围绕垂直管并具有给水入口（50）和蒸汽出口（52）的流体流动体积。 PWR具有操作状态，其中通过在OTSG的管内流动的一次冷却剂发出的热量将注入进料水入口处的流体流量的给水转化为蒸汽，并且蒸汽在蒸汽处从流体流量排出出口。

10. 发明授权

US09275763B2 Nuclear fuel rod spacer grid and framework and assembly comprising such a grid 有权
标题翻译：核燃料棒间隔栅格和包括这种栅格的框架和组件
公开(公告)号：US09275763B2
公开(公告)日：2016-03-01
申请号：US12741572
申请日：2008-10-30
申请人： Noemie Gomez , Angelo Beati , Dominique Hertz , Thierry Muller
发明人： Noemie Gomez , Angelo Beati , Dominique Hertz , Thierry Muller
IPC分类号： G21C3/34 , G21C3/352 , G21C3/334
CPC分类号： G21C3/34 , G21C3/334 , G21Y2002/302 , G21Y2004/30 , Y02E30/40
摘要： A grid including at least two meshed grid parts intended to be superposed in a longitudinal direction, each grid part extending in a transverse plane, and the grid parts being moveable one relative to the other in at least one transverse direction between an open configuration for the insertion of nuclear fuel rods in the longitudinal direction through the grid parts, and a closed configuration allowing each fuel rod inserted through the grid parts to be clamped transversely between the grid parts. According to one aspect of the invention, the grid includes elements for transversely immobilizing the grid parts in the closed configuration, the immobilizing elements being designed to engage as the superposed grid parts are moved closer together in the longitudinal direction.
摘要翻译：包括至少两个网格部分的网格，所述网格部分旨在在纵向方向上重叠，每个网格部分在横向平面中延伸，并且网格部分可以在至少一个横向方向上相对于另一个相对移动，将核燃料棒沿纵向方向插入格栅部分，并且封闭构造允许插入通过格栅部分的每个燃料棒横向地夹在网格部分之间。根据本发明的一个方面，所述网格包括用于将栅格部分横向固定在封闭构造中的元件，所述固定元件设计成当所述叠置的栅格部分在纵向方向上更靠近地移动时被接合。

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