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1. 发明授权

US11935663B2 Control rod drive system for nuclear reactor 有权
公开(公告)号：US11935663B2
公开(公告)日：2024-03-19
申请号：US17081753
申请日：2020-10-27
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
IPC分类号： G21C7/12 , G21C7/10 , G21C7/117 , G21C9/004 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/10 , G21D1/00
CPC分类号： G21C7/12 , G21C7/10 , G21C7/117 , G21C9/004 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/10 , G21D1/00 , G21D1/006 , Y02E30/30
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.

2. 发明授权

US11901088B2 Method of heating primary coolant outside of primary coolant loop during a reactor startup operation 有权
公开(公告)号：US11901088B2
公开(公告)日：2024-02-13
申请号：US17088815
申请日：2020-11-04
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Gerald Leo Rajkumar
IPC分类号： G21C15/243 , G21C7/32 , G21C15/26 , G21D1/00 , G21C13/073
CPC分类号： G21C15/243 , G21C7/32 , G21C15/26 , G21C13/073 , G21D1/00 , G21D1/006 , Y02E30/30
摘要： A method for heating primary coolant in a nuclear reactor system during system start-up. A primary coolant loop fluidly couples together a reactor vessel and a steam generating vessel. The primary coolant loop is filled with primary coolant. A portion of the primary coolant is taken from the primary coolant loop and placed into a start-up sub-system. The portion is heated while in the sub-system to form a heated portion of the primary coolant. The heated portion is returned into the primary coolant loop. The method allows for the primary coolant to be heated to a no-load operating temperature.

3. 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.

4. 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.

5. 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.

6. 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.

7. 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.

8. 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。

9. 发明申请

US20140321596A1 PASSIVE REACTOR COOLING SYSTEM 有权
标题翻译：被动式反应器冷却系统
公开(公告)号：US20140321596A1
公开(公告)日：2014-10-30
申请号：US14289525
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 , G21Y2002/207 , G21Y2004/302 , Y02E30/40
摘要： A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.
摘要翻译：具有被动冷却能力的核反应堆冷却系统在反应堆关闭事件期间可操作而无可用电力。在一个实施例中，系统包括具有核燃料芯的反应器容器和与其流体耦合的蒸汽发生器。主冷却剂在反应堆容器和蒸汽发生器之间的流动回路中循环，以在蒸汽发生器中加热产生蒸汽的二次冷却剂。蒸汽流入含有浸没浸没管束的冷却水库存的热交换器。蒸汽在热交换器中冷凝并返回到蒸汽发生器，形成闭合的流动回路，其中二次冷却剂流由自然重力通过来自加热和冷却循环的密度变化来驱动。在其他实施例中，冷却系统构造成使用浸没式管束热交换器直接提取和冷却一次冷却剂。

10. 发明公开

US20240266083A1 NUCLEAR STEAM SUPPLY AND START-UP SYSTEM, PASSIVELY-COOLED SPENT NUCLEAR FUEL POOL SYSTEM AND METHOD THEREFOR, COMPONENT COOLING WATER SYSTEM FOR NUCLEAR POWER PLANT, PASSIVE REACTOR COOLING SYSTEM, STEAM GENERATOR FOR NUCLEAR STEAM SUPPLY SYSTEM 审中-公开
公开(公告)号：US20240266083A1
公开(公告)日：2024-08-08
申请号：US18437013
申请日：2024-02-08
申请人： SMR Inventec, LLC
发明人： Krishna P. SINGH , Joseph Gerald Leo RAJKUMAR
IPC分类号： G21C15/243 , G21C7/32 , G21C13/073 , G21C15/26 , G21D1/00
CPC分类号： G21C15/243 , G21C7/32 , G21C15/26 , G21C13/073 , G21D1/00 , G21D1/006 , Y02E30/30
摘要： A nuclear steam supply system having a start-up sub-system for heating a primary coolant. The nuclear steam supply system comprises a reactor vessel with core comprising nuclear fuel, and steam generating vessel fluidly coupled to the reactor vessel. A primary coolant loop formed within the reactor vessel and the steam generating vessel circulates primary coolant through the loop. A steam supply start-up sub-system is fluidly coupled to the primary coolant loop. The start-up sub-system is configured and operable to: (1) extract and receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant back into the primary coolant loop.

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