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31. 发明授权

US6053652A Apparatus for performing jet pump riser pipe repairs 失效
标题翻译：用于执行喷射泵提升管修理的装置
公开(公告)号：US6053652A
公开(公告)日：2000-04-25
申请号：US834315
申请日：1997-04-15
申请人： Gerald A. Deaver , Siamak Bourbour , Don Schrein , John G. Erbes
发明人： Gerald A. Deaver , Siamak Bourbour , Don Schrein , John G. Erbes
IPC分类号： G21C19/02 , F04F5/54 , F16D1/00 , G21C20060101 , G21C13/032 , G21C15/22 , G21C15/25 , G21C19/20
CPC分类号： F16L13/06 , F16L55/179 , G21C15/25 , G21C19/207 , Y02E30/40 , Y10S403/09 , Y10T403/18 , Y10T403/4345 , Y10T403/4611 , Y10T403/5781
摘要： Apparatus for supporting the lower riser assembly of a jet pump in a reactor pressure vessel (RPV) of a nuclear reactor. In one embodiment of the apparatus, the clamp assembly provides structural rigidity to the lower rise assembly. The clamp assembly includes a lower thermal sleeve clamp and a riser clamp. The lower thermal sleeve clamp is positioned adjacent an interface between the elbow and the thermal sleeve of the jet pump riser pipe assembly. The riser clamp is secured to the riser pipe of the jet pump riser pipe assembly at a location adjacent an interface between the riser pipe and the elbow. The lower thermal sleeve clamp and the riser clamp also are coupled to each other so that as the respective clamps are secured to the lower riser assembly.
摘要翻译：用于在核反应堆的反应堆压力容器（RPV）中支撑喷射泵的下提升管组件的装置。在该装置的一个实施例中，夹具组件向下升组件提供结构刚性。夹具组件包括下部热套筒夹和提升管夹。下部热套筒夹具位于喷射泵提升管组件的弯头和热套筒之间的界面附近。提升管夹在与提升管和肘部之间的界面相邻的位置处固定到喷射泵提升管组件的提升管。下部热套筒夹具和提升管夹具也彼此联接，使得当相应的夹具固定到下部提升管组件时。

32. 发明授权

US4844274A Pressure vessel having a connection stub with a thermal protector 失效
标题翻译：具有与热保护器的连接短管的压力容器
公开(公告)号：US4844274A
公开(公告)日：1989-07-04
申请号：US202809
申请日：1988-06-03
申请人： Zvonimir Sterk
发明人： Zvonimir Sterk
IPC分类号： B65D90/00 , F16J12/00 , F16L41/08 , F22B37/22 , G21C13/032
CPC分类号： G21C13/032 , F22B37/225 , F22B37/228 , Y02E30/40
摘要： A pressure vessel assembly includes a pressure vessel with a vessel wall having a connection stub with a stub wall. A thermal protector for the connection stub in the form of a first tube extends substantially parallel to the stub wall. The first tube has an inner surface, one end disposed at the stub wall and another free end extending into the pressure vessel. Brackets are disposed on the inner surface of the tube between the other free end and the stub wall. A second tube extends into the connection stub beyond the one end of the first tube. The second tube has slits formed therein defining prongs therebetween connected to the brackets.
摘要翻译：压力容器组件包括具有容器壁的压力容器，所述容器壁具有与短管壁的连接短截线。用于第一管形式的连接短管的热保护器基本上平行于短管壁延伸。第一管具有内表面，一端设置在短截壁处，另一端延伸到压力容器中。支架设置在管的内表面之间的另一个自由端和短截壁之间。第二管延伸到第一管的一端之外的连接短管中。第二管具有形成在其间的缝隙，其间连接有支架。

33. 发明授权

US4782727A Process of replacing a sleeve mounted within a pipe, and devices for carrying out that process 失效
标题翻译：更换安装在管道内的套筒的过程以及用于执行该过程的装置
公开(公告)号：US4782727A
公开(公告)日：1988-11-08
申请号：US39200
申请日：1987-04-16
申请人： Alain Martin , Philippe Maillard
发明人： Alain Martin , Philippe Maillard
IPC分类号： F16L55/179 , F16L55/18 , F28F11/02 , G21C13/032 , B23B5/00
CPC分类号： G21C13/032 , F16L55/179 , F16L55/18 , F28F11/02 , Y02E30/40 , Y10T82/16442 , Y10T82/16951 , Y10T82/22
摘要： Apparatus for replacing thermal sleeves in pressurized-water nuclear power station circuits in a rapid, automatic manner producing minimal debris. A two-part frame is fixed to the outer wall of the sleeve coaxially therewith, each part of the frame carried one part of a two-part rotatable element, which in turn carries a support for a cross-cutting tool. The tool support is moved toward the axis of the frame but stopped just before the too breaks into the interior space of the sleeve.
摘要翻译：用于以快速，自动的方式更换加压水核电站电路中的热套筒的装置，产生最小的碎片。两部分框架与套管同轴地固定在套筒的外壁上，框架的每个部分承载了两部分可旋转元件的一部分，该部件又带有用于横切工具的支撑。工具支撑件朝向框架的轴线移动，但在太过分入套筒的内部空间之前停止。

34. 发明授权

US4600553A Reactor cavity 失效
标题翻译：反应器腔
公开(公告)号：US4600553A
公开(公告)日：1986-07-15
申请号：US462851
申请日：1983-02-01
申请人： Leonard R. Katz , Walter E. Desmarchais
发明人： Leonard R. Katz , Walter E. Desmarchais
IPC分类号： G21C13/00 , G21C9/004 , G21C13/032 , G21C13/036 , G21C13/10 , G21D1/00 , G21C9/00
CPC分类号： G21C9/004 , G21C13/036 , Y02E30/40
摘要： A reactor cavity surrounding a reactor coolant inlet or outlet pipe is designed to reduce pressurization of the cavity in the event of a LOCA pipe break therein.
摘要翻译：围绕反应堆冷却剂入口或出口管的反应器空腔设计成在其中存在LOCA管道破裂的情况下减小空腔的加压。

35. 发明授权

US4369893A Sealing arrangement with annular flexible disc 失效
标题翻译：密封结构与环形软盘
公开(公告)号：US4369893A
公开(公告)日：1983-01-25
申请号：US235371
申请日：1981-02-19
申请人： William E. Pennell , Charles A. Honigsberg
发明人： William E. Pennell , Charles A. Honigsberg
IPC分类号： G21C13/00 , F16J15/02 , F16J15/08 , F16J15/10 , F16J15/16 , F16L41/02 , F16L41/08 , G21C13/028 , G21C13/032 , F16J15/06
CPC分类号： G21C13/028 , F16J15/025 , F16J15/0887 , F16L41/084 , G21C13/032 , Y02E30/40
摘要： Fluid sealing arrangements including an annular shaped flexible disc having enlarged edges disposed within channel-shaped annular receptacles which are spaced from one another. The receptacles form an annular region for contacting and containing the enlarged edges of the disc, and the disc is preloaded to a conical configuration. The disc is flexibly and movably supported within the receptacles so that unevenly distributed relative motion between the components containing the receptacles is accommodated without loss of sealing contact between the edges of the disc and the walls of the receptacles.
摘要翻译：流体密封装置包括环形软盘，其具有设置在通道形状的环形容器中的具有扩大的边缘，其彼此间隔开。容器形成用于接触和容纳盘的扩大边缘的环形区域，并且盘被预加载成圆锥形构造。该盘被灵活地并且可移动地支撑在容器内，使得容纳容纳部件的部件之间的不均匀分布的相对运动被容纳，而不会损失盘的边缘和容器的壁之间的密封接触。

36. 发明授权

US4356147A Fluid tight and thermally insulated coupling assembly 失效
标题翻译：流体密封和热绝缘耦合组件
公开(公告)号：US4356147A
公开(公告)日：1982-10-26
申请号：US17767
申请日：1979-03-05
申请人： Bo Borrman , Knud Engedal
发明人： Bo Borrman , Knud Engedal
IPC分类号： F16L59/16 , G21C13/032 , G21C13/036 , G21C19/32
CPC分类号： G21C13/036 , F16L59/16 , Y02E30/40
摘要： A coupling assembly for joining an inlet nozzle with a conduit assembly extending concentrically therein, to provide a fluid-tight and thermally insulated flow passageway for introducing cold water into a nuclear reactor pressure vessel and the like.The coupling assembly comprises a protective sleeve surrounding the conduit assembly and wedged into abutting contact with an end portion of the conduit assembly and an inner surface of the inlet nozzle to form a fluid-tight seal therebetween. A fluid insulating medium having a decreasing temperature gradient is positioned between a portion of the protective sleeve and the surrounding inlet nozzle to create a similar decreasing temperature gradient within the inlet nozzle, in order to protect the nozzle against thermal shocks resulting from the difference in temperature between the relatively warm reactor pressure vessel surrounding the inlet nozzle and the relatively cold water flowing through the inlet nozzle.
摘要翻译：用于将入口喷嘴与其中同心地延伸的导管组件接合的联接组件，以提供用于将冷水引入核反应堆压力容器等的流体密封且热绝缘的流动通道。联接组件包括围绕导管组件并楔入与导管组件的端部邻接接触的保护套管和入口喷嘴的内表面，以在它们之间形成流体密封的密封。具有降低的温度梯度的流体绝缘介质位于保护套筒的一部分和周围的入口喷嘴之间，以在入口喷嘴内产生类似的降低的温度梯度，以保护喷嘴免受由温度差引起的热冲击在相对温暖的反应堆压力容器周围的入口喷嘴和相对冷的水流过入口喷嘴。

37. 发明授权

US4238291A Device for coupling pipelines in nuclear reactor pressure vessels, especially in boiling water reactors 失效
标题翻译：用于在核反应堆压力容器，特别是沸水反应堆中连接管道的装置
公开(公告)号：US4238291A
公开(公告)日：1980-12-09
申请号：US869362
申请日：1978-01-13
申请人： Walter Neuenfeldt , Milan Sulic , Gerd Pollak
发明人： Walter Neuenfeldt , Milan Sulic , Gerd Pollak
IPC分类号： G21C13/032 , G21C9/00
CPC分类号： G21C13/032 , Y02E30/40
摘要： For coupling pipelines in a nuclear reactor pressure vessel with a core flood line formed of a first line section extending sealingly through a housing wall of the reactor pressure vessel and secured thereto, and a second line section disposed in the interior of the pressure vessel and couplable sealingly to the first line section, the second line section extending through a cover of a core container and terminating in the core container, a device includes means for forming the second line section and the core container cover into a structural unit so that the second line section together with the core container cover is liftable out of and insertable into the pressure vessel upon opening the latter for selectively inspecting, servicing and both inspecting and servicing the same, the first and second line sections having a mutual coupling location, means defining coaxial sealing surfaces disposed at the mutual coupling location for holding the first and second line sections in mutual engagement, the coaxial sealing surfaces having a contact pressure therebetween deriving from weight per se and bracing force of the core container cover oriented in axial direction of the pressure vessel, the first and the second line sections being in mutual spring-biased engagement at the mutual coupling location thereof.
摘要翻译：用于在核反应堆压力容器中耦合管道，其中具有由密封地延伸通过反应堆压力容器的壳体壁并固定到其上的第一管线部分形成的核心溢流管线，以及设置在压力容器内部并可连接的第二管线部分密封地连接到第一线段，第二线段延伸穿过芯容器的盖并终止在芯容器中，装置包括用于将第二线段和芯容器盖形成为结构单元的装置，使得第二线部分与核心容器盖一起可打开并可插入压力容器中，用于选择性地检查，维修和检查并维护该容器盖，第一和第二管线部分具有相互联接的位置，设置在相互联接位置处的表面，用于将第一和第二线段相互保持所述同轴密封表面具有来自重量本身的接触压力和沿着压力容器的轴向方向定向的芯容器盖的支撑力，所述第一和第二线段在相互的相互弹簧偏置接合耦合位置。

38. 发明授权

US11189386B2 Replacing a thermal sleeve in a reactor vessel head adapter 有权
公开(公告)号：US11189386B2
公开(公告)日：2021-11-30
申请号：US16262037
申请日：2019-01-30
申请人： Westinghouse Electric Company LLC
发明人： Eric M. Benacquista , Anthony J. Mastopietro , Bryan M. Wilson , Nicholas A. Szweda
IPC分类号： G21C13/067 , G21C13/032 , G21C19/00 , G21C15/00 , G21C7/12 , G21C15/12 , G21C19/20
摘要： A method of replacing a damaged thermal sleeve in a reactor vessel head adapter that connects a control rod drive mechanism to a reactor vessel head includes the steps of accessing the damaged thermal sleeve, removing the damaged thermal sleeve, and obtaining a replacement thermal sleeve having an elongated tubular body, a flanged region, and a plurality of slots defined in the elongated tubular body, each slot having a width which is sufficient to narrow a maximum outside diameter of the flanged region from a first diameter to a second diameter. The method further includes altering the maximum outside diameter of the flanged region on the replacement thermal sleeve, inserting the replacement thermal sleeve into an opening of a tubular member from an underside of the reactor vessel head, and expanding the maximum outside diameter of the flanged region into a recess of the reactor vessel head adapter.

39. 发明授权

US11120920B2 Steam generator for nuclear steam supply system 有权
公开(公告)号：US11120920B2
公开(公告)日：2021-09-14
申请号：US16682495
申请日：2019-11-13
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Gearald Leo Rajkumar
IPC分类号： G21C15/18 , G21C15/14 , F22B1/02 , G21C13/04 , G21C15/22 , G21C15/26 , G21D1/00 , G21C15/257 , G21C13/032
摘要： A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.

40. 发明授权

US10403407B2 Managing dynamic forces on a nuclear reactor system 有权
公开(公告)号：US10403407B2
公开(公告)日：2019-09-03
申请号：US14182985
申请日：2014-02-18
申请人： NUSCALE POWER, LLC
发明人： Tamas Liszkai
IPC分类号： G21C9/04 , G21C13/024 , E04H9/02 , G21C9/00 , G21C13/032 , G21C13/04 , G21D1/00 , G21D3/04 , G21C1/32
摘要： A nuclear reactor seismic isolation assembly includes an enclosure that defines a volume; a plastically-deformable member mounted, at least in part, within the volume; and a stretching member moveable within the enclosure to plastically-deform the plastically-deformable member in response to a dynamic force exerted on the enclosure.

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