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1. 发明授权

US10923239B2 Moving an entire nuclear reactor core as a unitary structure 有权
公开(公告)号：US10923239B2
公开(公告)日：2021-02-16
申请号：US15822704
申请日：2017-11-27
申请人： SMR INVENTEC, LLC
发明人： Krishna P. Singh , P. Stefan Anton , Peter Stefanovic
IPC分类号： G21C5/06 , G21C3/30 , G21C5/14 , G21C11/06 , G21C19/19 , G21C1/06 , G21C3/32 , G21C19/07 , G21C19/18 , G21C3/33
摘要： An entire nuclear fuel core comprising a plurality of fuel assemblies is preassembled in a nuclear fuel cartridge having a self-supporting unitary support structure. During a refueling operation, the unitary support structure is moved into a nuclear reactor vessel. The unitary support structure may be formed by top and bottom core plates coupled together by vertically-oriented connecting rods which compress the fuel assemblies therebetween. A plurality of reflector wall segments circumscribe the core and are the coupled together between the core plates by the connecting rods which are coupled to the core plates. The connecting rods may extend through the wall segments.

2. 发明申请

US20210012913A1 LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM 有权
公开(公告)号：US20210012913A1
公开(公告)日：2021-01-14
申请号：US16883592
申请日：2020-05-26
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21C13/02 , G21C15/12 , G21D1/00
摘要： A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.

3. 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.

4. 发明申请

US20150170766A1 NUCLEAR FUEL CORE, NUCLEAR FUEL CARTRIDGE, AND METHODS OF FUELING AND/OR DEFUELING A NUCLEAR REACTOR 有权
标题翻译：核燃料核，核燃料燃料箱，以及燃料和/或排除核反应堆的方法
公开(公告)号：US20150170766A1
公开(公告)日：2015-06-18
申请号：US14413807
申请日：2013-07-09
申请人： SMR INVENTEC, LLC
发明人： Krishna P. Singh , P. Stefan Anton , Peter Stefanovic
IPC分类号： G21C3/30 , G21C5/06
CPC分类号： G21C3/30 , G21C1/06 , G21C3/32 , G21C5/06 , G21C5/14 , G21C11/06 , G21C19/07 , G21C19/18 , G21C19/32 , G21F5/008 , G21F5/12 , Y02E30/40 , Y10T29/49947
摘要： A portable nuclear fuel cartridge comprising a unitary support structure and a plurality of nuclear fuel assemblies that collectively form a nuclear fuel core. The nuclear fuel core is integrated into the unitary support structure to collectively form a self-supporting assemblage than can be lifted as a single unit. In another aspect, the invention is a method of fueling and/or defueling a nuclear reactor utilizing a nuclear fuel cartridge that is loaded and/or unloaded from the nuclear reactor as a single unit. In another aspect, a nuclear reactor core is provided that comprises a nuclear fuel core comprising; a plurality of first nuclear fuel assemblies, each of the plurality of first nuclear fuel assemblies having a first transverse cross-sectional configuration; and a plurality of second nuclear fuel assemblies, each of the plurality of second nuclear fuel assemblies having a second transverse cross-sectional configuration that is different than the first transverse cross-sectional configuration.
摘要翻译：一种便携式核燃料盒，其包括统一形成核燃料芯的单一支撑结构和多个核燃料组件。核燃料芯整合到单一支撑结构中，以形成一个自支撑组合，而不仅仅是一个单一的单元。在另一方面，本发明是一种利用核燃料盒加油和/或排空核反应堆的方法，所述核反应堆作为单个装置从核反应堆装载和/或卸载。在另一方面，提供了一种核反应堆堆芯，其包括核燃料芯，包括：多个第一核燃料组件，所述多个第一核燃料组件中的每一个具有第一横向横截面构造; 和多个第二核燃料组件，所述多个第二核燃料组件中的每一个具有不同于第一横截面构造的第二横截面构型。

5. 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.

6. 发明授权

US11094421B2 Fail-safe control rod drive system for nuclear reactor 有权
公开(公告)号：US11094421B2
公开(公告)日：2021-08-17
申请号：US16744144
申请日：2020-01-15
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
IPC分类号： G21C7/14 , G21C9/02 , G21C7/12
摘要： A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

7. 发明授权

US10580539B2 Nuclear reactor shroud 有权
公开(公告)号：US10580539B2
公开(公告)日：2020-03-03
申请号：US15715631
申请日：2017-09-26
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
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.

8. 发明授权

US10573419B2 Fail-safe control rod drive system for nuclear reactor 有权
公开(公告)号：US10573419B2
公开(公告)日：2020-02-25
申请号：US15288436
申请日：2016-10-07
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
IPC分类号： G21C7/14 , G21C7/12 , G21C9/02
摘要： A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

9. 发明授权

US09916910B2 Passively-cooled spent nuclear fuel pool system and method therefor 有权
公开(公告)号：US09916910B2
公开(公告)日：2018-03-13
申请号：US14620465
申请日：2015-02-12
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21C19/07 , G21C19/04 , G21C13/02 , 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 comprising: a spent nuclear fuel pool comprising a body of liquid water having a surface level, at least one spent nuclear fuel rod submerged therein that heats the water; a lid covering the spent nuclear fuel pool to create a hermetically sealed vapor space between the surface level and the lid; and a passive heat exchange sub-system including a riser conduit comprising first and second riser inlet sections and a primary riser section that receives water vapor therefrom. Each riser inlet section has a respective inlet positioned in a respective section of the vapor space. A downcomer receives and condenses water vapor from the primary section forming condensed water vapor. A return conduit fluidly coupled to the downcomer and having an outlet located in the body of liquid water returns the condensed water vapor thereto.

10. 发明申请

US20140321597A1 LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM 审中-公开
标题翻译：冷却故障反应器冷却系统
公开(公告)号：US20140321597A1
公开(公告)日：2014-10-30
申请号：US14289545
申请日：2014-05-28
申请人： SMR Inventec, LLC
发明人： Krishna P. SINGH , Joseph RAJKUMAR
IPC分类号： G21C15/18
CPC分类号： G21C15/18 , G21C9/004 , G21C13/02 , G21C15/12 , G21D1/00 , G21D1/006 , Y02E30/40
摘要： A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.
摘要翻译：具有被动冷却功能的核反应堆冷却系统，可在冷却液事故损失（LOCA）下运行，无需电力。该系统包括具有位于反应器井中的核燃料芯的反应器容器。一个内置储水罐与反应器井流体耦合并保存冷却水的库存。在LOCA事件期间，坦克用水充满水。最终，通过来自反应器的衰变热加热的水蒸发产生蒸汽。蒸汽流入容纳式热交换器并冷凝。冷凝物在封闭的流动回路系统中返回到反应器，其中流动可以通过重力从水的相位和密度的变化中循环。在一个实施例中，热交换器可以是安装在由散热器包围的内部容纳容器的壁上的散热器管道的阵列。

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