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1. 发明授权

US11798697B2 Passive heat removal system for nuclear reactors 有权
公开(公告)号：US11798697B2
公开(公告)日：2023-10-24
申请号：US17159743
申请日：2021-01-27
申请人： TerraPower, LLC
发明人： Pavel Hejzlar , Peter McNabb
IPC分类号： G21C1/32 , G21C5/10 , G21C13/04 , G21C13/024 , G21C15/18 , G21C9/00 , G21C3/33 , G21C1/02 , G21C15/247 , G21C19/04 , H02K44/06 , G21C15/12 , F16K99/00 , F16K15/00
CPC分类号： G21C5/10 , G21C13/024 , G21C13/04 , F16K15/00 , F16K99/0021 , G21C1/028 , G21C1/326 , G21C3/33 , G21C9/00 , G21C15/12 , G21C15/185 , G21C15/247 , G21C19/04 , H02K44/06
摘要： A nuclear reactor is configured with an intermediate coolant loop for transferring thermal energy from the reactor core for a useful purpose. The intermediate coolant loop includes a bypass flowpath with an air heat exchanger for dumping reactor heat during startup and/or shutdown. A fluidic diode along the bypass flowpath asymmetrically restricts flow across the bypass flowpath, inhibiting flow in a first flow direction during a full power operating condition and allowing a relatively uninhibited flow in a second direction during a startup and/or shut down low power operating condition.

2. 发明授权

US11728049B2 Reactor core and control elements supported by a reactor vessel head 有权
公开(公告)号：US11728049B2
公开(公告)日：2023-08-15
申请号：US17164820
申请日：2021-02-01
申请人： TerraPower, LLC
发明人： Charles Gregory Freeman , Calen Kaneko , Christopher A Martin , Sean T Mosier
IPC分类号： G21C5/10 , G21C13/04 , G21C13/024 , G21C15/18 , G21C9/00 , G21C3/33 , G21C1/02 , G21C15/247 , G21C19/04 , H02K44/06 , G21C1/32 , G21C15/12
CPC分类号： G21C5/10 , G21C13/024 , G21C13/04 , G21C1/028 , G21C1/326 , G21C3/33 , G21C9/00 , G21C15/12 , G21C15/185 , G21C15/247 , G21C19/04 , H02K44/06
摘要： A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

3. 发明授权

US11476010B2 Cooling method for reactor molten core melt and cooling control system for reactor molten core 有权
公开(公告)号：US11476010B2
公开(公告)日：2022-10-18
申请号：US16627741
申请日：2018-12-28
申请人： Joint-stock company “Atomenergoproekt” , Joint Stock Company “Science and Innovations”
发明人： Aleksandr Stalevich Sidorov , Nadezhda Vasilevna Sidorova
IPC分类号： G21C9/016 , G21C15/18 , G21C17/112 , G21C19/04 , G21C17/00 , G21C9/00 , G21C19/313
摘要： The invention relates to safe operation support systems of nuclear power plants (NPPs) at severe accidents, including methods and systems for cooling and cooling control of the reactors molten core. The invention increases safety of NPP and cooling efficiency of the molten core of a reactor. The invention increases the efficiency of cooling the molten core of a reactor by safely removing the heat load from the molten metal mirror, ensuring the elimination of vapor explosions. The invention changes the principle of cooling the reactor molten core, in that after the molten core destroys the reactor vessel, the conditions for subsequent cooling of the molten metal are determined by the characteristics of the trap casing, but not of the reactor.

4. 发明申请

US20190237205A1 DIRECT HEAT EXCHANGER FOR MOLTEN CHLORIDE FAST REACTOR 审中-公开
公开(公告)号：US20190237205A1
公开(公告)日：2019-08-01
申请号：US16264112
申请日：2019-01-31
申请人： TerraPower, LLC
发明人： Ryan Abbott , Anselmo T. Cisneros , Kevin Kramer , James A. Roecker , Daniel J. Walter , Kent E. Wardle
IPC分类号： G21C3/44 , G21C19/04 , G21C19/28 , G21C7/30 , G21C1/22
CPC分类号： G21C3/44 , F22B37/00 , G21C1/03 , G21C1/22 , G21C1/326 , G21C3/54 , G21C7/30 , G21C11/06 , G21C15/18 , G21C19/04 , G21C19/28 , G21D1/006 , G21D1/04
摘要： A molten chloride fast reactor (MCFR) includes a plurality of reflectors defining a central core having a core geometric center. A flow channel fluidically connected to the central core. The flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core. A primary heat exchanger (PHX) disposed outside the central core and between the outlet flow channel and the inlet flow channel. The MCFR also includes a decay heat heat exchanger (DHHX). At least a portion of the DHHX is disposed above the core geometric center, and a fuel salt is configured to circulate at least partially through the outlet flow channel, the DHHX, the PHX, the inlet flow channel, and the central core.

5. 发明申请

US20190057788A1 JET PUMP PLUG SEAL AND METHODS OF MAKING AND USING SAME 审中-公开
公开(公告)号：US20190057788A1
公开(公告)日：2019-02-21
申请号：US15884072
申请日：2018-01-30
申请人： EXELON GENERATION COMPANY, LLC
发明人： Nicholas P. Osmond , Vikram Shah
IPC分类号： G21C19/04 , F16L55/11 , F16L55/10
摘要： A jet pump plug and methods of forming a seal with a plurality of nozzles of a jet pump are disclosed. The plug has a plug body and a washer embedded within and bonded to the plug body. The washer has a center opening that cooperates with the plug body to define a central bore extending through the plug and the central bore can be configured to receive a fastener. A plurality of the disclosed plugs can be positioned in alignment with a respective nozzle, with each plug being sealed to the respective nozzle to form a seal.

6. 发明申请

US20180277264A1 PASSIVELY-COOLED SPENT NUCLEAR FUEL POOL SYSTEM 审中-公开
公开(公告)号：US20180277264A1
公开(公告)日：2018-09-27
申请号：US15996868
申请日：2018-06-04
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21C19/04 , G21C13/02 , G21C19/07 , G21C11/00
CPC分类号： G21C15/18 , G21C11/00 , G21C13/02 , G21C19/04 , G21C19/07 , Y02E30/40
摘要： A passively-cooled spent nuclear fuel pool system in one embodiment includes a containment vessel comprising a thermally conductive shell and an annular reservoir surrounding the shell that holds a liquid coolant forming a heat sink. A spent fuel pool is disposed inside the containment vessel and includes a body of water in contact with a first peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The first peripheral sidewall of the spent fuel pool is formed by a portion of the shell of the containment vessel adjacent to the fuel pool, thereby defining a shared common heat transfer wall. The heat transfer wall operates to transfer heat from the body of water in the spent fuel pool to the heat sink to cool the body of water. The heat transfer wall comprises metal in one embodiment.

7. 发明授权

US08917808B2 Device for handling a fuel assembly 有权
标题翻译：用于处理燃料组件的装置
公开(公告)号：US08917808B2
公开(公告)日：2014-12-23
申请号：US12440633
申请日：2007-08-21
申请人： Sture Helmersson
发明人： Sture Helmersson
IPC分类号： G21C19/00 , G21C19/04 , G21C19/10
CPC分类号： G21C19/04 , G21C19/10 , G21Y2002/207 , G21Y2002/303 , G21Y2004/30 , G21Y2004/40
摘要： The invention refers to a device and a method for handling a fuel assembly (3), which comprises a number of fuel rods extending between a lower part and an upper part of the fuel assembly, a debris filter located in the lower part of the fuel assembly and a casing surrounding the fuel rods. The device comprises a lifting device (15) for engaging, during a lifting operation, a fuel assembly located in a reactor vessel (1) and lifting the fuel assembly upwards and out from the reactor vessel. A conduit member is connected to the upper part of the fuel assembly. A pump (32) creates a flow of water through the conduit member and the fuel assembly during the lifting operation. The flow has such a size that possible debris particles contained in and/or immediately beneath the debris filter at least are retained in and/or immediately beneath the debris filter during the lifting operation.
摘要翻译：本发明涉及一种用于处理燃料组件（3）的装置和方法，燃料组件（3）包括在燃料组件的下部和上部之间延伸的多个燃料棒，位于燃料的下部的碎屑过滤器组件和围绕燃料棒的套管。该装置包括提升装置（15），用于在提升操作期间接合位于反应器容器（1）中的燃料组件，并将燃料组件从反应器容器向上和向外提升。导管构件连接到燃料组件的上部。泵（32）在提升操作期间通过导管构件和燃料组件产生水流。流动具有这样的尺寸，使得在提升操作期间，包含在碎屑过滤器中和/或紧邻碎片过滤器之下的可能的碎屑颗粒至少保留在碎屑过滤器的和/或紧邻下方。

8. 发明授权

US5377241A Effluent container 失效
标题翻译：出水容器
公开(公告)号：US5377241A
公开(公告)日：1994-12-27
申请号：US135091
申请日：1993-10-12
申请人： Benedict Kazirskis , Edward W. Saxon , Bettadapur N. Sridhar
发明人： Benedict Kazirskis , Edward W. Saxon , Bettadapur N. Sridhar
IPC分类号： G21C19/20 , G21C19/02 , G21C19/04
CPC分类号： G21C19/02 , G21Y2002/40 , G21Y2002/501 , G21Y2004/501
摘要： An effluent container has two halves which fit together to form a cylinder, open at the top, for catching residual contaminated water falling from the control rod drive (CRD) housing under the influence of gravity when the seal between the CRD housing and the CRD is broken. The container has an aperture which fits around the extension rod that supports the CRD when the mounting bolts are removed. The container halves are held together by elastic cords stretched between hooks on the side-walls. The effluent container has L-shaped slots which hook onto the bracing bolts of the sway brace system to support the container in position for catching falling water. Spilled water drains out of the container to a sump.
摘要翻译：出水容器具有两个半部，两个半部组合在一起，形成一个在顶部开口的气缸，用于当CRD壳体和CRD之间的密封是重力时，在重力作用下捕获从控制杆驱动器（CRD）壳体落下的残留污染水破碎。当卸下安装螺栓时，容器具有围绕延伸杆安装的孔，该孔支撑CRD。容器半部通过在侧壁上的钩之间拉伸的弹性帘线保持在一起。流出物容器具有L形槽，其钩住摇摆支架系统的支撑螺栓，以将容器支撑在适当位置以捕获落水。溢出的水从集装箱中排出一个水槽。

9. 发明授权

US4173511A Control rod blow out protection system 失效
标题翻译：控制杆吹出保护系统
公开(公告)号：US4173511A
公开(公告)日：1979-11-06
申请号：US270319
申请日：1972-07-10
申请人： Joseph R. Dietrich , William S. Flinn , Malcolm D. Groves
发明人： Joseph R. Dietrich , William S. Flinn , Malcolm D. Groves
IPC分类号： G21C7/12 , G21C19/04
CPC分类号： G21C19/04 , G21C7/12 , G21Y2002/203 , G21Y2002/304 , G21Y2004/30 , G21Y2004/302 , G21Y2004/40 , Y02E30/39
摘要： An absorber element "blow-out" protection system for a nuclear reactor having a pressure vessel through which a coolant is circulated. The blow-out protection system includes devices which hydraulically couple groups of guide tubes in which the absorber elements move, the coupling devices limiting coolant lift flow rate to a level commensurate with the raising of individual absorber elements but insufficient to raise a plurality of absorber elements simultaneously.
摘要翻译：一种用于具有冷却剂循环的压力容器的核反应堆的吸收元件“吹出”保护系统。吹出保护系统包括液压耦合吸收体元件移动的导管组的装置，耦合装置将冷却剂升力流量限制到与各个吸收元件的升高相当的水平，但不足以升高多个吸收元件同时。

10. 发明授权

US3855060A Bottom actuated reactor control rod devices 失效
标题翻译：底部启动反应器控制装置
公开(公告)号：US3855060A
公开(公告)日：1974-12-17
申请号：US27047072
申请日：1972-07-10
申请人： COMBUSTION ENG
发明人： DIETRICH J , GROVES M
IPC分类号： G21C7/16 , G21C17/12 , G21C19/04
CPC分类号： G21C17/12 , G21C7/16 , G21C19/04 , G21Y2002/301 , G21Y2002/50 , G21Y2004/30 , G21Y2004/304 , G21Y2004/40 , Y02E30/39
摘要： A hydraulic system for controlling the position of neutron absorber elements with respect to a reactor fuel assembly, the control system incorporating means for preventing absorber element ''''blow-out'''' in the event of a pressure vessel rupture. The blow-out protection means includes closed end cylinders which define extensions of the guide tubes in which the absorber elements move and pistons attached to the absorber elements and movable in said guide tube extensions; each piston cooperating with a guide tube extension to define a restricted flow path for fluid in said tube extension above the absorber element.
摘要翻译：一种用于控制中子吸收器元件相对于反应堆燃料组件的位置的液压系统，该控制系统包括用于在压力容器破裂的情况下防止吸收元件“吹出”的装置。吹出保护装置包括封闭的端部气缸，其限定引导管的延伸部分，吸收器元件在其中移动，活塞附接到吸收器元件并可在所述引导管延伸部中移动; 每个活塞与引导管延伸部协作以限定在吸收器元件上方的所述管延伸部中的流体的限制流动路径。

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