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11. 发明授权

US09773576B2 Nuclear reactor shroud 有权
公开(公告)号：US09773576B2
公开(公告)日：2017-09-26
申请号：US14771018
申请日：2014-02-27
申请人： SMR INVENTEC, LLC
发明人： Krishna P. Singh , Indresh Rampall , Joseph Gerald Leo Rajkumar
IPC分类号： G21C15/24 , G21C13/02 , G21C15/243 , G21C9/04
CPC分类号： G21C15/24 , G21C9/04 , G21C13/02 , G21C15/243 , Y02E30/40
摘要： A nuclear reactor in one embodiment includes a cylindrical, body having an internal cavity, a nuclear fuel core, and a shroud disposed in the cavity. The shroud comprises an inner shell, an outer shell and a plurality of intermediate shells disposed between the inner and outer shells. Pluralities of annular cavities are formed between the inner and outer shells which are filled with primary coolant such as demineralized water. The coolant-filled annular cavities may be sealed at the top and bottom and provide an insulating effect to the shroud. In one embodiment, the shroud may comprise a plurality of vertically-stacked self-supported shroud segments which are coupled together.

12. 发明授权

US09773574B2 Systems and methods for enhancing isolation of high-temperature reactor containments 有权
公开(公告)号：US09773574B2
公开(公告)日：2017-09-26
申请号：US14533055
申请日：2014-11-04
申请人： THE REGENTS OF THE UNIVERSITY OF CALIFORNIA
发明人： Per F. Peterson
IPC分类号： G21C1/04 , G21C11/08 , G21C13/02 , G21C13/10 , G21C15/12 , G21C15/18
CPC分类号： G21C11/08 , G21C13/02 , G21C13/10 , G21C15/12 , G21C15/18 , Y02E30/35
摘要： A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

13. 发明申请

US20170117063A1 PASSIVE COOLING TO COLD SHUTDOWN 审中-公开
公开(公告)号：US20170117063A1
公开(公告)日：2017-04-27
申请号：US14923277
申请日：2015-10-26
申请人： NuScale Power, LLC
发明人： Michael KELLER , Ross SNUGGERUD , Tamas LISZKAI
IPC分类号： G21C15/18 , G21C13/02 , G21C17/00 , G21C15/24
CPC分类号： G21C15/18 , G21C13/00 , G21C13/02 , G21C15/24 , G21C17/00 , Y02E30/40
摘要： A cooling system for a reactor module includes a reactor pressure vessel that houses primary coolant and a steam generator that lowers a temperature of the reactor pressure vessel by transferring heat from the primary coolant to a secondary coolant that circulates through the steam generator. The steam generator releases at least a portion of the secondary coolant as steam. Additionally, the cooling system includes a containment vessel that at least partially surrounds the reactor vessel in a containment region. The containment region is dry during normal operation of the reactor module. A controller introduces a source of water into the containment region in response to a non-emergency shut down of the reactor module. The source of water is located external to the containment vessel, and the water is introduced into the containment region after the steam generator has initially lowered the temperature of the reactor pressure vessel in response to releasing the steam.

14. 发明授权

US09530525B2 Locking fastener for securing components in a nuclear reactor 有权
标题翻译：用于将组件固定在核反应堆中的锁紧紧固件
公开(公告)号：US09530525B2
公开(公告)日：2016-12-27
申请号：US13586998
申请日：2012-08-16
申请人： Paul K. DeSantis , Andrew D. Klush
发明人： Paul K. DeSantis , Andrew D. Klush
IPC分类号： F16B39/28 , G21C7/12 , G21C13/02 , F16B39/10
CPC分类号： G21C7/12 , F16B39/108 , G21C13/02 , Y02E30/39
摘要： A threaded fastener includes a head, a threaded shank extending from a bottom face of the head along a longitudinal axis of the fastener, and an annular flange oriented transverse to the longitudinal axis and surrounding the bottom face of the head. A surface has a receiving hole in which the shank of the threaded fastener is disposed with the bottom face of the head contacting the surface. The surface further has a crimping recess spaced apart from the receiving hole. A portion of the annular flange overlaps and is deformed into the crimping recess. The fastener may be a screw or bolt. In the case of a bolt, a nut engages the distal end of the threaded shank. The nut also includes an annular flange that is deformed into a crimping recess on a surface proximate to the nut.
摘要翻译：螺纹紧固件包括头部，沿着紧固件的纵向轴线从头部的底面延伸的螺纹柄，以及横向于纵向轴线并围绕头部的底面的环形凸缘。表面具有容纳孔，螺纹紧固件的柄部设置成与头部的底面接触表面。表面还具有与接收孔间隔开的压接凹部。环形凸缘的一部分与压接凹部重叠并变形。紧固件可以是螺钉或螺栓。在螺栓的情况下，螺母接合螺纹柄的远端。螺母还包括环形凸缘，其变形成靠近螺母的表面上的压接凹部。

15. 发明授权

US09478320B2 Method for in-core instrumentation withdrawal from the core of a pressurized water reactor 有权
标题翻译：核心仪表从压水反应堆核心退出的方法
公开(公告)号：US09478320B2
公开(公告)日：2016-10-25
申请号：US14461555
申请日：2014-08-18
申请人： Westinghouse Electric Company LLC
发明人： Radu O. Pomirleanu , Alexander W. Harkness
IPC分类号： G21C19/19 , G21C13/02 , G21C19/20 , G21C1/32
CPC分类号： G21C19/19 , G21C1/322 , G21C5/10 , G21C13/02 , G21C17/116 , G21C19/205 , Y02E30/40
摘要： A method of removing the upper internals assembly from a nuclear reactor pressure vessel for refueling that simultaneously disconnects two or more of the in-core instrument thimble assemblies from the reactor vessel penetrations through which their signal cables extend. The signal cables are connected to the penetrations with an electrical connector that supports the two or more in-core instrumentation thimble assembly signal leads. Before the electrical connector is disconnected, water in the vessel is lowered below the connection so that the process is performed in a dry environment.
摘要翻译：从用于加油的核反应堆压力容器移除上部内件组件的方法，其同时将两个或更多个核心内仪器套管组件与其信号电缆延伸穿过的反应堆容器穿透断开。信号电缆通过支撑两个或多个核心仪表套管组件信号引线的电连接器连接到穿孔。在电连接器断开之前，容器中的水被降低到连接下方，使得该过程在干燥的环境中进行。

16. 发明申请

US20160260505A1 FASTENERS FOR NUCLEAR REACTOR SYSTEMS 审中-公开
标题翻译：核反应堆系统的紧固件
公开(公告)号：US20160260505A1
公开(公告)日：2016-09-08
申请号：US15055336
申请日：2016-02-26
申请人： NuScale Power, LLC
发明人： Seth Cadell , Tamas R. Liszkai
IPC分类号： G21C3/33
CPC分类号： G21C3/331 , G21C5/10 , G21C11/06 , G21C13/02 , G21C19/19 , Y02E30/40
摘要： Various embodiments are directed towards a nuclear latch assembly. The assembly includes a latch housing and a latch mechanism. The latch mechanism includes a projection member. The latch mechanism provides a biasing force on the projection member. Unless an opposing force on the projection member counterbalances the biasing force, the projection member at least partially projects from a surface of the latch housing. The assembly may include a biasing member that provides the biasing force on the projection member. The assembly may include a bolt. The bolt includes a longitudinal axis. A bore included in the housing is sized to receive the bolt. When the bore receives the bolt, the housing is rotatable about the longitudinal axis of the bolt. The latch mechanism includes a side bore that receives the projection member, the biasing member, and a disk intermediate the projection member and the biasing member.
摘要翻译：各种实施例针对核闩锁组件。组件包括闩锁壳体和闩锁机构。闩锁机构包括突出部件。闩锁机构在突起构件上提供偏置力。除非突出构件上的相反的力抵消偏置力，突起构件至少部分地从闩锁壳体的表面突出。组件可以包括偏置构件，该偏压构件在突出构件上提供偏压力。组件可以包括螺栓。螺栓包括纵向轴线。包括在壳体中的孔的尺寸被设计成接收螺栓。当孔接收螺栓时，壳体可以围绕螺栓的纵向轴线旋转。闩锁机构包括容纳突出构件，偏压构件的侧孔和在突出构件和偏置构件之间的盘。

17. 发明授权

US09373423B2 Method of accessing a core of a nuclear reactor 有权
标题翻译：访问核反应堆核心的方法
公开(公告)号：US09373423B2
公开(公告)日：2016-06-21
申请号：US14734368
申请日：2015-06-09
申请人： Westinghouse Electric Company LLC
发明人： Eric M. Weisel , Kenneth V. Margotta , Daniel Walus , Thomas J. Schildkamp , Joseph J. Hahn , Michael D. Heibel
IPC分类号： G21C17/10 , G21C19/02 , G21C13/02 , G21C17/116
CPC分类号： G21C19/02 , G21C13/02 , G21C17/10 , G21C17/116 , Y02E30/40
摘要： A telescoping guide for extraction and reinsertion support handling of in-core instrument thimble assemblies in the area above the upper support plate in the upper internals of a pressurized water reactor. The telescoping guides extend between the upper ends of the upper internals support columns and an axially movable instrumentation grid assembly which is operable to simultaneously raise the telescoping guides and extract the in-core instrument thimble assemblies from the reactor fuel assemblies.
摘要翻译：用于提取和重新插入的伸缩引导件支持在压力水反应堆的上部内部中的上支撑板上方的区域中处理芯内仪器套管组件。伸缩引导件在上部内部支撑柱的上端和可轴向移动的仪表栅格组件之间延伸，其可操作以同时升高伸缩引导件并从反应堆燃料组件提取核心内仪器套管组件。

18. 发明申请

US20160042818A1 OUTLET NOZZLE OF NUCLEAR REACTOR 审中-公开
标题翻译：核反应堆出口喷嘴
公开(公告)号：US20160042818A1
公开(公告)日：2016-02-11
申请号：US14779913
申请日：2013-04-23
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD.
发明人： Ho Rim MOON , Young Sheop PARK
IPC分类号： G21C15/24
CPC分类号： G21C15/24 , G21C13/02 , G21C13/036 , G21C17/003 , Y02E30/40
摘要： The present invention relates to an outlet nozzle of a nuclear reactor. More specifically, in the outlet nozzle of a nuclear reactor which is provided to a reactor vessel and into which the coolant discharged from the nozzle of a structure in the reactor is introduced, the outlet nozzle of a nuclear reactor has an inclination part formed at one side of the outlet nozzle such that the inclination part is inclined at a predetermined angle from the outside end to the inside thereof. The present invention has an effect, wherein the one side of the outlet nozzle into which the coolant is introduced from the nozzle of a structure in the nuclear reactor is inclined or rounded such that an inspection robot (ASME Sec XI IWB-3512) for inspecting the presence of a defect in the coupling state of the reactor while moving along the inside surface of the reactor vessel in the reactor can move to the lower side of the reactor, and thus the volumetric inspection of the reactor by the inspection robot can be freely and continuously advanced such that the volumetric inspection can be carried out to 100% without any excluded portion for welded parts. In addition, the stability of the nuclear reactor can be more effectively verified as the volumetric inspection is carried out to 100%.
摘要翻译：本发明涉及核反应堆的出口喷嘴。更具体地说，在提供给反应堆容器的核反应堆的出口喷嘴中，从反应器中的结构的喷嘴排出的冷却剂被引入其中，核反应堆的出口喷嘴具有形成在一个使得倾斜部分从外端到内部倾斜预定的角度。本发明具有这样的效果，其中从核反应堆中的结构的喷嘴引入冷却剂的出口喷嘴的一侧倾斜或倒圆，使得用于检查的检查机器人（ASME Sec XI IWB-3512）在反应器内的反应器容器的内表面移动时，反应器的耦合状态的缺陷的存在可以移动到反应器的下侧，因此检查机器人的反应器的体积检查可以是自由的并持续进行，使得体积检查可以执行到100％，没有任何排除部分的焊接部件。另外，由于体积检测进行到100％，核反应堆的稳定性可以得到更有效的验证。

19. 发明申请

US20150357059A1 FLOW ALLOCATION APPARATUS, LOWER REACTOR INTERNAL OF REACTOR, AND REACTOR 审中-公开
标题翻译：流量分配装置，反应器内部反应器和反应器
公开(公告)号：US20150357059A1
公开(公告)日：2015-12-10
申请号：US14759735
申请日：2014-01-08
申请人： STATE NUCLEAR POWER TECHNOLOGY CORPORATION LTD. , SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE
发明人： Shaoxuan LIN , Yejia LIANG , Zonghua DING , Ming ZHANG , Qing YU , Wei ZHANG , Weida YAO , Fan YU
IPC分类号： G21C13/02 , G21C5/10
CPC分类号： G21C13/02 , G21C5/10 , G21C7/32 , G21C15/00 , Y02E30/40
摘要： A flow distribution device (3) for a reactor, a lower internals (100) of a reactor and a reactor are provided. The lower internals (100) includes: a lower core support plate (2) defining a coolant hole therethrough; a flow distribution device (3) mounted on the lower core support plate (2) and including a distribution annular plate (8) and a distribution bottom plate (9); a vortex suppression plate (7) disposed below the distribution bottom plate (9); a support column (4) defining an upper end connected with the lower core support plate (2) and a lower end passing through the distribution bottom plate (9) to connect with the vortex suppression plate (7); an energy absorption device (5) defining an upper end connected with the vortex suppression plate (7); and an anti-break bottom plate (6) disposed on the lower end of the energy absorption device (5).
摘要翻译：提供了用于反应器的流量分配装置（3），反应器的下部内部（100）和反应器。下部内件（100）包括：下部芯部支撑板（2），其限定穿过其中的冷却剂孔; 安装在所述下芯支撑板（2）上并且包括分配环形板（8）和分配底板（9）的流量分配装置（3）; 设置在分配底板（9）下方的涡流抑制板（7）; 限定与所述下芯支撑板（2）连接的上端的支撑柱（4）和穿过所述分配底板（9）以与所述涡流抑制板（7）连接的下端; 限定与所述涡流抑制板（7）连接的上端的能量吸收装置（5）; 以及设置在所述能量吸收装置（5）的下端的防破裂底板（6）。

20. 发明申请

US20150221403A1 FACILITY FOR REDUCING RADIOACTIVE MATERIAL AND NUCLEAR POWER PLANT HAVING THE SAME 审中-公开
标题翻译：减少放射性物质的设施和具有相同功能的核电厂
公开(公告)号：US20150221403A1
公开(公告)日：2015-08-06
申请号：US14469499
申请日：2014-08-26
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE
发明人： Young In KIM , Kyung Jun KANG , Keung Koo KIM , Hun Sik HAN , Ju Hyeon YOON , Jae Joo HA , Dae Hyun HWANG , Suhn CHOI , Joo Hyung MOON , Soo Jai SHIN
IPC分类号： G21D3/04 , G21D1/02 , G21F1/04
CPC分类号： G21D3/04 , G21C9/00 , G21C9/004 , G21C13/02 , G21C15/18 , G21D1/02 , Y02E30/40
摘要： The present invention provides a facility for reducing radioactive material comprising: a cooling water storage unit installed inside a containment and formed to store cooling water; a boundary unit forming a boundary of radioactive material inside the containment and surrounding a reactor coolant system installed inside the containment to prevent a radioactive material from releasing from the reactor coolant system or a pipe connected with the reactor coolant system to the containment; a connecting pipe connected with an inner space of the boundary unit and the cooling water storage unit to guide a flow of a fluid caused by a pressure difference between the boundary unit and the cooling water storage unit from the boundary unit to the cooling water storage unit; and a sparging unit disposed to be submerged in the cooling water stored in the cooling water storage unit and connected with the connecting pipe to sparge the fluid that has passed through the connecting pipe and the radioactive material contained in the fluid to the cooling water storage unit.
摘要翻译：本发明提供了一种减少放射性物质的设备，包括：冷却水存储单元，其安装在容纳物内并形成以存储冷却水; 边界单元，形成容纳物内的放射性物质的边界，并围绕安装在安全壳内的反应堆冷却剂系统，以防止放射性物质从反应堆冷却剂系统或与反应堆冷却剂系统连接的管道释放到容纳物; 与边界单元的内部空间连接的连接管和冷却水存储单元，用于将边界单元和冷却水存储单元之间的压力差引起的流体流从边界单元引导到冷却水存储单元 ; 以及喷射单元，其被设置为浸没在存储在冷却水存储单元中的冷却水中并与连接管连接，以将已经通过连接管的流体和流体中包含的放射性物质喷射到冷却水存储单元。

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