公开(公告)号：US20240404717A1

公开(公告)日：2024-12-05

申请号：US18793503

申请日：2024-08-02

Applicant: Palvannanathan Ganesan

Inventor： Palvannanathan Ganesan

IPC: G21C9/00 ,  G21C9/016 ,  G21C13/04 ,  G21C15/18

Abstract: An underground nuclear power reactor system has a hollow blast tunnel which extends from one end of a containment member. The system includes a nuclear reactor vessel and other components that may be positioned on a movable support member or on a bottom wall of the containment member. A blast tunnel, which defines a blast chamber, has a plurality of spaced-apart debris deflectors positioned therein. The blast chamber has an upper wall with a roof opening formed therein which is selectively closed by a roof portion. If the reactor needs to be repaired or replaced, the roof portion is opened so that the reactor vessel can through the roof opening. If the reactor vessel explodes, a blast therefrom drives debris therefrom through a blast door and into the blast chamber where the deflectors reduce blast force as the debris passes through the blast chamber.

公开(公告)号：US10726962B2

公开(公告)日：2020-07-28

申请号：US15413770

申请日：2017-01-24

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  P. Stephan Anton ,  Ranga Nadig ,  Indresh Rampall

IPC: G21C15/26 ,  G21C1/08 ,  G21C7/32 ,  G21C13/04 ,  G21C15/12 ,  G21D1/00

Abstract: A nuclear reactor system that, in one embodiment, utilizes natural circulation to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heat exchange subsystem is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heat exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground.

公开(公告)号：US10510452B2

公开(公告)日：2019-12-17

申请号：US16507637

申请日：2019-07-10

Applicant: SMR Inventec, LLC

Inventor： Krishna P. Singh ,  Joseph Gearald Leo Rajkumar

IPC: G21C15/14 ,  G21C15/22 ,  G21C13/04 ,  F22B1/02 ,  G21D1/00 ,  G21C15/26 ,  G21C15/257 ,  G21C13/032 ,  G21C15/18

Abstract: 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.

公开(公告)号：US10096387B2

公开(公告)日：2018-10-09

申请号：US14507672

申请日：2014-10-06

Applicant: Robert F. Bennion

Inventor： Robert F. Bennion

IPC: G21C1/24 ,  G21C7/02 ,  G21C1/30 ,  G21C7/34 ,  G21D1/00 ,  G21G4/02 ,  G21C13/04

Abstract: A self-regulating inherently safe apparatus for generating neutrons is described herein that includes a reaction chamber that sustains neutron generation when filled with a liquid fissionable material and an expansion chamber that dampens neutron generation from the liquid fissionable material in response to expansion of the liquid fissionable material into the expansion chamber. Consequently, the apparatus may substantially dampen neutron generation for operating temperatures above a nominal operating temperature without requiring active or external control and inherently limit neutron generation to a maximum desired output power. Also described herein is a self-regulating system and corresponding method for extracting energy from fissionable material that includes a neutron generator that generates neutrons from a liquid fissionable material and a sub-critical collection of fissionable material that generates a non-sustaining plurality of fission events from neutrons received from the neutron generator.

公开(公告)号：US20170213606A1

公开(公告)日：2017-07-27

申请号：US15483466

申请日：2017-04-10

Applicant: BWXT mPower, Inc.

Inventor： Tyler A. Edwards ,  Scott J. Shargots

IPC: G21C13/028 ,  G21C15/02 ,  G21C1/32 ,  G21C13/04

CPC classification number: G21C13/028 ,  G21C1/322 ,  G21C13/02 ,  G21C13/04 ,  G21C15/00 ,  G21C15/02 ,  Y02E30/40

Abstract: A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.

公开(公告)号：US20170062081A1

公开(公告)日：2017-03-02

申请号：US15119611

申请日：2015-02-17

Applicant: Joint Stock Company "Atomenergoproekt"

Inventor： Marat Renadovich MUSTAFIN ,  Aleksandr Grigoryevich GERASIMENKO ,  Valentin Ivanovich TSAPALIKOV ,  Nikolai Anatolyevich IVANOV ,  Gennady Alekseevich NOVIKOV ,  Arnold Borisovich TIKHOMIROV ,  Ivan Mikhailovich KHAUSTOV

IPC: G21C13/036 ,  H02G3/22 ,  G21C13/04

CPC classification number: G21C13/036 ,  G21C13/04 ,  G21C17/116 ,  H02G3/22 ,  Y02E30/40

Abstract: The invention relates to the field of electrical engineering, and specifically to sealed inlets of electrical circuits into a sealed area of a multi-layered containment shell of a nuclear power station. This design can be used in passages through an external and an internal wall which are subject to relative mutual displacement as a consequence of a seismic phenomenon or thermal expansion of the walls and passage. The problem addressed by the present invention is that of increasing the operating reliability of a sealed cable inlet when high-voltage electrical conductors which have little bending capacity are used. The problem addressed is achieved in that the sealed cable inlet through an external and an internal wall of a containment shell of a nuclear power station comprises an embedded pipe (3) which is arranged in the internal wall (1), with an inlet section (44) of a cable (2) fixed rigidly within said pipe. A means for compensating for a relative movement between the cable (2) and the external wall (11) is mounted in the external wall (11) coaxially with respect to the pipe (3). The compensating means has a tube (19) with a bellows (24) on the external end plane (20) and with a second analogous bellows (25) which is mounted symmetrically on the opposite end plane (21) of the tube (19) at the internal surface (18) of the external wall (11). The free ends (30) and (31) of the two bellows (24) and (25) are of conical design and have internal surfaces (28) and (29) which are support elements for an outlet section (46) of the cable (2), which is arranged freely in the tube (19) with a gap (47) relative to the internal surface (49) of the tube (19). The gap (47) between the braiding (48) along the external surface of the cable (2) and the internal surface (49) of the tube (19) is selected using a design calculation. The gap (47) must not be less than the value of maximum orthogonal thermo-seismic movement in one plane of the internal wall (1) relative to the external wall (11) and change in the coaxial position of the cable (2) in the tube (19).

公开(公告)号：US20160099082A1

公开(公告)日：2016-04-07

申请号：US14507672

申请日：2014-10-06

Applicant: Robert F. Bennion

Inventor： Robert F. Bennion

IPC: G21C7/02 ,  G21C13/04 ,  G21C1/24 ,  G21C19/02

CPC classification number: G21C7/02 ,  G21C1/24 ,  G21C1/30 ,  G21C7/34 ,  G21C13/04 ,  G21D1/00 ,  G21G4/02 ,  Y02E30/39

Abstract: A self-regulating inherently safe apparatus for generating neutrons is described herein that includes a reaction chamber that sustains neutron generation when filled with a liquid fissionable material and an expansion chamber that dampens neutron generation from the liquid fissionable material in response to expansion of the liquid fissionable material into the expansion chamber. Consequently, the apparatus may substantially dampen neutron generation for operating temperatures above a nominal operating temperature without requiring active or external control and inherently limit neutron generation to a maximum desired output power. Also described herein is a self-regulating system and corresponding method for extracting energy from fissionable material that includes a neutron generator that generates neutrons from a liquid fissionable material and a sub-critical collection of fissionable material that generates a non-sustaining plurality of fission events from neutrons received from the neutron generator.

Abstract translation: 本文描述了用于产生中子的自调节固有的安全装置，其包括当填充液体可裂变材料时维持中子产生的反应室和响应于液体可裂变材料的膨胀而从液体可裂变材料产生中子的膨胀室 材料进入膨胀室。 因此，该装置可以基本上抑制操作温度高于额定工作温度的中子产生，而不需要主动或外部控制，并且固有地将中子产生限制到最大期望的输出功率。 本文还描述了一种用于从可裂变材料提取能量的自调节系统和相应方法，其包括从液体可裂变材料产生中子的中子发生器和产生不间断多个裂变事件的可分裂材料的亚临界收集 来自中子发生器的中子。

公开(公告)号：US06888909B2

公开(公告)日：2005-05-03

申请号：US10401284

申请日：2003-03-27

Applicant: David R. Forsyth ,  David A. Altman ,  Kevin G. Bethune ,  Michael F. Hankinson ,  Robert H. McFetridge

Inventor： David R. Forsyth ,  David A. Altman ,  Kevin G. Bethune ,  Michael F. Hankinson ,  Robert H. McFetridge

IPC: G21C20060101 ,  G21C5/10 ,  G21C9/00 ,  G21C13/00 ,  G21C13/02 ,  G21C13/04 ,  G21C15/12

CPC classification number: G21C15/12 ,  G21C5/10 ,  G21C13/02 ,  G21C13/04 ,  G21Y2002/103 ,  G21Y2002/201 ,  G21Y2004/302 ,  Y02E30/40

Abstract: A reactor pressure vessel supports the flanges of a core barrel assembly and an upper support plate. These flanges have aligned holes for diverting inlet coolant water to the vessel head for cooling the head. The aligned holes have different cross-sectional areas for controlling unexpected backflow of coolant water from the vessel head around the periphery of the upper support plate.

Abstract translation: 反应堆压力容器支撑芯筒组件和上支撑板的凸缘。 这些法兰具有对准的孔，用于将入口冷却水转向容器头以冷却头部。 对准的孔具有不同的横截面面积，用于防止来自容器头部的冷却水从围绕上支撑板周边的意外回流。

公开(公告)号：US4673548A

公开(公告)日：1987-06-16

申请号：US646312

申请日：1984-08-31

Applicant: William S. Betts, Jr. ,  J. Larry Pickering ,  William E. Black

Inventor： William S. Betts, Jr. ,  J. Larry Pickering ,  William E. Black

IPC: G21C5/10 ,  G21C11/08 ,  G21C13/04

CPC classification number: G21C11/08 ,  G21C5/10 ,  Y02E30/40

Abstract: A thermal barrier/core support for the fuel core of a nuclear reactor having a metallic cylinder secured to the reactor vessel liner and surrounded by fibrous insulation material. A top cap is secured to the upper end of the metallic cylinder that locates and orients a cover block and post seat. Under normal operating conditions, the metallic cylinder supports the entire load exerted by its associated fuel core post. Disposed within the metallic cylinder is a column of ceramic material, the height of which is less than that of the metallic cylinder, and thus is not normally load bearing. In the event of a temperature excursion beyond the design limits of the metallic cylinder and resulting in deformation of the cylinder, the ceramic column will abut the top cap to support the fuel core post.

Abstract translation: 用于核反应堆的燃料芯的热障/核心支撑件，其具有固定到反应堆容器衬里并被纤维绝缘材料包围的金属圆筒。 顶盖固定在金属圆筒的上端，定位和定位一个盖块和柱座。 在正常工作条件下，金属圆筒支撑由相关联的燃料芯柱施加的整个载荷。 在金属圆筒内设置一列陶瓷材料，其高度小于金属圆筒，因此通常不承受负荷。 在温度偏移超过金属圆筒的设计限制并导致气缸变形的情况下，陶瓷柱将抵靠顶盖以支撑燃料芯柱。

公开(公告)号：US4239598A

公开(公告)日：1980-12-16

申请号：US956319

申请日：1978-10-31

Applicant: Elman E. Wade

Inventor： Elman E. Wade

IPC: G21C13/024 ,  G21C13/04

CPC classification number: G21C13/024 ,  Y02E30/40 ,  Y10T403/32622 ,  Y10T403/7094

Abstract: A support column for a heavy component of a liquid metal fast breeder reactor heat transport system which will deflect when the pipes leading coolant to and from the heavy component expand or contract due to temperature changes includes a vertically disposed pipe, the pipe being connected to the heavy component by two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles and the pipe being supported through two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles, each of the cylindrical surfaces bearing on a flat and horizontal surface.

Abstract translation: 用于液体金属快速增殖反应堆热输送系统的重组分的支撑柱，当导致冷却剂流出重物的管道由于温度变化而膨胀或收缩的管道将偏转时，该支撑柱将偏转包括垂直设置的管道， 重型部件由两个纵向间隔的摆线燕尾接头组成，其中每个燕尾榫的远端构成大直径圆筒的表面的一部分，并且这些大直径圆柱体的中心线以直角相交，并且管通过两个纵向间隔 摆线燕尾接头，其中每个燕尾形构件的远端构成大直径圆柱体的表面的一部分，并且这些大直径圆柱体的中心线以直角相交，每个圆柱形表面承载在平坦且水平的表面上。