公开(公告)号：WO2022040152A1

公开(公告)日：2022-02-24

申请号：PCT/US2021/046253

申请日：2021-08-17

Applicant: NUSCALE POWER, LLC ,  BOTHA, Derick ,  WALDEN, Michele

Inventor： BOTHA, Derick ,  WALDEN, Michele

IPC: F28D15/04 ,  F16L11/12 ,  F16L11/14 ,  F28F13/18 ,  F28F21/04 ,  F28F21/08

Abstract: Heat pipes and methods of forming heat pipes, such as for use in nuclear reactor systems, are described herein. A representative method of forming a heat pipe includes forming a first wicking structure from a first material and forming a second wicking structure on the first wicking structure. Forming the second wicking structure can include mixing a second material and a third material, and heating the mixture of the second material and the third material to a temperature (a) less than a melting temperature of the second material and (b) greater than a melting temperature of the third material to melt the third material. The method can further include cooling the mixture of the second material and the third material to below the melting temperature of the third material such that the third material solidifies to bond together a plurality of particles of the second material into a porous structure.

公开(公告)号：WO2019164584A3

公开(公告)日：2019-08-29

申请号：PCT/US2018/068040

申请日：2018-12-28

Applicant: NUSCALE POWER, LLC

Inventor： LINIK, Larry ,  BRISTOL, Ben ,  ROOKS, Kenneth ,  CALLAWAY, Allyson

IPC: G21C7/08 ,  G21C9/02 ,  G21C9/033 ,  G21C13/02 ,  G21C7/22

Abstract: Implementations of a nuclear reactor system include a passive boron injection system operable to release an amount of boron into a containment vessel sufficient to shut down a nuclear fission reaction or maintain the nuclear fission reaction in a sub-critical state. Implementations of a nuclear reactor system include a reactor module that is free of any control rod assemblies. Implementations of a nuclear reactor system include a reactor module that includes a control rod assembly system that is operable to position control rod assemblies in only two discrete positions.

公开(公告)号：WO2019133398A1

公开(公告)日：2019-07-04

申请号：PCT/US2018/066569

申请日：2018-12-19

Applicant: NUSCALE POWER, LLC

Inventor： LISZKAI, Tamas

IPC: G21C7/12 ,  G21C13/04 ,  G21C15/02

CPC classification number: G21C7/14 ,  G21C7/10 ,  G21C7/12 ,  G21C13/04 ,  G21C13/0735 ,  G21C15/02

Abstract: In some embodiments, a nuclear reactor vessel comprises a containment vessel for a reactor pressure vessel (RPV); a control rod drive mechanism (CRDM) located in the containment vessel, the CRDM including drive motors configured to move control rods into and out of a nuclear reactor core located in the RPV; and a partition extending across a portion of the containment vessel configured to retain the drive motors in a separate fluid-tight barrier region within the containment vessel. Other embodiments may be disclosed and/or claimed.

公开(公告)号：WO2017074507A1

公开(公告)日：2017-05-04

申请号：PCT/US2016/030013

申请日：2016-04-29

Applicant: NUSCALE POWER, LLC

Inventor： KELLER, Michael ,  SNUGGERUD, Ross ,  LISZKAI, Tamas

IPC: G21C13/00 ,  G21C15/18

CPC classification number: G21C15/18 ,  G21C13/00 ,  G21C13/02 ,  G21C15/24 ,  G21C17/00 ,  Y02E30/40

Abstract: 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.

Abstract translation: 用于反应堆模块的冷却系统包括容纳一次冷却剂的反应堆压力容器和蒸汽发生器，该蒸汽发生器通过将热量从一次冷却剂传递到循环的二次冷却剂来降低反应堆压力容器的温度 通过蒸汽发生器。 蒸汽发生器将至少一部分二次冷却剂作为蒸汽释放。 另外，冷却系统包括在容纳区域中至少部分地围绕反应器容器的容器。 在反应器模块的正常运行期间，容纳区域是干燥的。 响应于反应堆模块的非紧急关闭，控制器将水源引入容纳区域。 水源位于安全壳外部，并且在蒸汽发生器响应释放蒸汽而初始降低反应堆压力容器的温度之后，将水引入安全壳区域。

公开(公告)号：WO2016122743A4

公开(公告)日：2016-09-22

申请号：PCT/US2015060144

申请日：2015-11-11

Applicant: NUSCALE POWER LLC

Inventor： HARRIS SCOTT G

IPC: G21C13/02

CPC classification number: G21C15/02 ,  G21C13/022 ,  Y02E30/40

Abstract: A system for draining a containment vessel may include a drain inlet located in a lower portion of the containment vessel. The containment vessel may be at least partially filled with a liquid, and the drain inlet may be located below a surface of the liquid. The system may further comprise an inlet located in an upper portion of the containment vessel. The inlet may be configured to insert pressurized gas into the containment vessel to form a pressurized region above the surface of the liquid, and the pressurized region may operate to apply a surface pressure that forces the liquid into the drain inlet. Additionally, a fluid separation device may be operatively connected to the drain inlet. The fluid separation device may be configured to separate the liquid from the pressurized gas that enters the drain inlet after the surface of the liquid falls below the drain inlet.

Abstract translation: 用于排放安全壳容器的系统可以包括位于安全壳容器下部的排放入口。 容纳容器可以至少部分地填充有液体，并且排水入口可以位于液体的表面下方。 该系统还可以包括位于安全壳上部的入口。 入口可以构造成将加压气体插入到安全壳中以在液体表面上方形成加压区域，并且加压区域可以操作以施加迫使液体进入排出口的表面压力。 另外，流体分离装置可以可操作地连接到排水入口。 流体分离装置可构造成在液体表面落入排水入口下方之后将液体与进入排水入口的加压气体分离。

公开(公告)号：WO2016028514A3

公开(公告)日：2016-04-14

申请号：PCT/US2015044163

申请日：2015-08-07

Applicant: NUSCALE POWER LLC

Inventor： MIRSKY STEPHEN M ,  REYES JOSE N

IPC: G21C15/18 ,  G21C19/07 ,  G21C19/08 ,  G21C19/40 ,  G21F7/015

CPC classification number: G21C19/07 ,  G21C15/18 ,  G21C19/08 ,  G21C19/40 ,  G21F7/015 ,  Y02E30/40

Abstract: A system (500) for storing nuclear fuel assemblies includes a plurality of cells housed within a support structure. A first cell (510) may house a first fuel assembly (550) and a second cell (520) may house a second fuel assembly. A plurality of compartments (560, 580) separate the plurality of cells and provide passageways for coolant entering a bottom end of the support structure to remove heat from the nuclear fuel assemblies. A first perforation (512) transfers coolant between the first cell and one or more of the compartments, and a second perforation (522) transfers coolant between the second cell and the one or more compartments. At least a portion of the coolant entering the bottom end of the support structure is transferred between the plurality of cells and the plurality of compartments. Two or more fuel storage racks may be stacked together in alternating fuel patterns to facilitate cooling the fuel assemblies with liquid or air.

Abstract translation: 用于存储核燃料组件的系统（500）包括容纳在支撑结构内的多个单元。 第一电池（510）可容纳第一燃料组件（550），第二电池（520）可容纳第二燃料组件。 多个隔室（560,580）分离多个单元并提供用于进入支撑结构的底端的冷却剂的通道，以从核燃料组件移除热量。 第一穿孔（512）在第一电池和一个或多个隔室之间传送冷却剂，第二穿孔（522）在第二电池和一个或多个隔室之间传输冷却剂。 进入支撑结构的底端的冷却剂的至少一部分在多个单元和多个隔室之间传递。 两个或多个燃料储存架可以以交替的燃料图案堆叠在一起，以便于用液体或空气冷却燃料组件。

公开(公告)号：WO2015099855A4

公开(公告)日：2015-09-11

申请号：PCT/US2014057693

申请日：2014-09-26

Applicant: NUSCALE POWER LLC

Inventor： SNUGGERUD ROSS ,  GOFF RUSSELL

IPC: G21C13/02 ,  G21C1/32 ,  G21C15/18 ,  G21C17/108

CPC classification number: G21C13/02 ,  G21C1/322 ,  G21C15/18 ,  G21C17/108 ,  Y02E30/40

Abstract: A neutron detection system (300, 400, 500, 600, 700, 800) may include a neutron detection device (325,425, 525, 625, 725, 825) located outside of a reactor vessel (2). The neutron detection device may be configured to detect neutrons generated within the reactor vessel. A containment region (14, 414, 514, 614, 714, 814) located intermediate the reactor vessel and a containment vessel may be configured to house a containment medium. A neutron path device (475, 575, 675, 775,875) may be at least partially located between the reactor vessel and the containment vessel, and the neutron path device may be configured to provide a neutron path (440, 540, 640, 740, 840) to the neutron detection device through a neutron path medium (430, 530, 630, 730, 830) contained within the neutron path device. A neutron attenuation coefficient associated with the neutron path medium may be smaller than a neutron attenuation coefficient associated with the containment medium.

Abstract translation: 中子探测系统（300,400,500,600,700,800）可以包括位于反应堆容器（2）外部的中子探测装置（325,425,525,625,725,825）。 中子检测装置可以被配置为检测反应堆容器内产生的中子。 位于反应器容器和容器的中间的容纳区域（14,414,514,614,714,814）可以构造成容纳容纳介质。 中子路径装置（475,575,675,775,875）可以​​至少部分地位于反应堆容器和安全壳之间，并且中子路径装置可以被配置为提供中子路径（440,540,640,740,850） 840）通过容纳在中子路径装置内的中子路径介质（430,530,630,730,830）输送到中子检测装置。 与中子路径介质相关联的中子衰减系数可以小于与容纳介质相关联的中子衰减系数。

公开(公告)号：WO2015099855A3

公开(公告)日：2015-08-13

申请号：PCT/US2014057693

申请日：2014-09-26

Applicant: NUSCALE POWER LLC

Inventor： SNUGGERUD ROSS ,  GOFF RUSSELL

IPC: G21C13/02 ,  G21C1/32 ,  G21C15/18 ,  G21C17/108

CPC classification number: G21C13/02 ,  G21C1/322 ,  G21C15/18 ,  G21C17/108 ,  Y02E30/40

Abstract: A neutron detection system (300, 400, 500, 600, 700, 800) may include a neutron detection device (325,425, 525, 625, 725, 825) located outside of a reactor vessel (2). The neutron detection device may be configured to detect neutrons generated within the reactor vessel. A containment region (14, 414, 514, 614, 714, 814) located intermediate the reactor vessel and a containment vessel may be configured to house a containment medium. A neutron path device (475, 575, 675, 775,875) may be at least partially located between the reactor vessel and the containment vessel, and the neutron path device may be configured to provide a neutron path (440, 540, 640, 740, 840) to the neutron detection device through a neutron path medium (430, 530, 630, 730, 830) contained within the neutron path device. A neutron attenuation coefficient associated with the neutron path medium may be smaller than a neutron attenuation coefficient associated with the containment medium.

Abstract translation: 中子检测系统（300,400,500,600,700,800）可以包括位于反应器容器（2）外部的中子检测装置（325,425,525,625,725,825）。 中子检测装置可以被配置为检测在反应堆容器内产生的中子。 位于反应器容器中间的容纳区域（14,414,514,614,714,814）和容纳容器可构造成容纳容纳介质。 中子路径装置（475,575,675,775,875）可以​​至少部分地位于反应堆容器和容纳容器之间，并且中子路径装置可以被配置为提供中子路径（440,540,640,740， 840）通过包含在中子路径装置内的中子路径介质（430,530,630,730,830）传送到中子检测装置。 与中子路径介质相关联的中子衰减系数可以小于与容纳介质相关联的中子衰减系数。

公开(公告)号：WO2015102742A1

公开(公告)日：2015-07-09

申请号：PCT/US2014/063127

申请日：2014-10-30

Applicant: NUSCALE POWER, LLC

Inventor： LISZKAI, Tamas ,  CADELL, Seth

IPC: G21C9/00 ,  G21C13/024 ,  G21C13/032 ,  G21C13/04 ,  G21D1/00 ,  G21D3/04 ,  G21C1/32

CPC classification number: G21C9/04 ,  G21C1/32 ,  G21C1/322 ,  G21C5/10 ,  G21C9/00 ,  G21C13/024 ,  G21C13/032 ,  G21C13/04 ,  G21D1/00 ,  G21D3/04 ,  Y02E30/40

Abstract: A system for attenuating seismic forces includes a reactor pressure vessel (2250) containing nuclear fuel and a containment vessel (2260) that houses the reactor pressure vessel (2250). Both the reactor pressure vessel (2250) and the containment vessel (2260) may include a bottom head (2210, 2220). Additionally, the system may include a base support (2270) that is configured to contact a support surface (2240) on which the containment vessel (2260) is positioned in a substantially vertical orientation. An attenuation device (2255, 2265) may be located between the bottom head (2210) of the reactor pressure vessel (2250) and the bottom head (2220) of the containment vessel (2260). Seismic forces that travel from the base support (2240) to the reactor pressure vessel (2250) via the containment vessel (2260) may be attenuated by the attenuation device (2255, 2265) in a direction that is substantially lateral to the vertical orientation of the containment vessel (2260).

Abstract translation: 一种用于衰减地震力的系统包括容纳核燃料的反应堆压力容器（2250）和容纳反应堆压力容器（2250）的容纳容器（2260）。 反应堆压力容器（2250）和容纳容器（2260）都可以包括底部头部（2210,2220）。 另外，系统可以包括基座支撑件（2270），其被构造成接触容纳容器（2260）所在的支撑表面（2240）处于基本垂直的方向。 衰减装置（2255,2655）可以位于反应堆压力容器（2250）的底部头部（2210）和容纳容器（2260）的底部头部（2220）之间。 经由容纳容器（2260）从基部支撑件（2240）传播到反应堆压力容器（2250）的地震力可以通过衰减装置（2255,2265）在基本上横向于垂直取向的方向上衰减 安全壳（2260）。

公开(公告)号：WO2015099868A1

公开(公告)日：2015-07-02

申请号：PCT/US2014/061161

申请日：2014-10-17

Applicant: NUSCALE POWER, LLC

Inventor： LISZKAI, Tamas ,  CADELL, Seth ,  KRUSKAMP, Alex ,  MALLETT, Matthew

IPC: G21C1/32 ,  G21C13/02 ,  G21C15/16

CPC classification number: G21C15/12 ,  F22B1/023 ,  G21C1/32 ,  G21C1/322 ,  G21C7/32 ,  G21C13/02 ,  G21C15/16 ,  G21D1/006 ,  Y02E30/40

Abstract: A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and a primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.

Abstract translation: 用于反应堆压力容器的热控制系统包括具有大致圆形形状的板，其连接到反应堆压力容器的壁。 板将反应堆压力容器分成上反应堆压力容器区域和下反应堆压力容器区域。 另外，板构造成在位于上反应堆压力容器区域内的加压容积和位于下反应堆压力容器区域内的主要冷却剂之间提供热障碍。 一个或多个增压室提供用于多个传热管通过反应堆压力容器的壁的通道。 多个传热管连接到板。