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公开(公告)号：US09589685B2
公开(公告)日：2017-03-07
申请号：US14289525
申请日：2014-05-28
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
CPC classification number: G21C15/18 , G21C9/004 , G21C13/02 , G21C15/12 , G21D1/00 , G21D1/006 , G21Y2002/207 , G21Y2004/302 , Y02E30/40
Abstract: 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.
Abstract translation: 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。
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公开(公告)号：US20170040070A1
公开(公告)日：2017-02-09
申请号：US15288436
申请日：2016-10-07
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
Abstract: 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.
Abstract translation: 用于核反应堆的控制棒驱动系统（CRDS）。 在一个实施例中，系统通常包括机械联接到可操作以沿着垂直轴直线地升高和降低驱动杆的控制杆驱动机构（CRDM）的驱动杆，包括多个控制杆的杆群控制组件（RCCA） 可插入核燃料芯中的驱动杆延伸部分（DRE）和在相对端可释放地联接到驱动杆和RCCA的驱动杆延伸部（DRE）。 CRDM包括用于将CRDM耦合到DRE的电磁体。 在断电或SCRAM的情况下，CRDM可以被配置为远离脱离DRE的RCCA，而不会释放或掉落与CRDM保持接合并位置的驱动杆。
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公开(公告)号：US20150255181A1
公开(公告)日：2015-09-10
申请号：US14437897
申请日：2013-10-25
Applicant: SMR INVENTEC, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
Abstract: A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant
Abstract translation: 在一个实施例中，公开了核发电系统和相关的动力循环，该系统包括通过包含核燃料的液压互连反应堆的主要冷却剂循环和共同限定蒸汽供应系统的蒸汽发生容器。 用于动力循环的液体二次冷却剂流过蒸汽发生容器，并通过主冷却剂转化为蒸汽以驱动涡轮发电机组的低压涡轮机。 离开涡轮机的蒸汽在返回到蒸汽供应系统之前被冷凝和加热，从而完成二次冷却剂流动循环。 在一个实施例中，二次冷却剂加热的大部分通过与主冷却剂的热交换而不是在二次冷却剂流动回路中的外部在蒸汽发生容器内发生。 这在初级冷却剂和次级冷却剂之间产生了温差，足以产生主冷却剂的自然热诱导的对流循环
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公开(公告)号：US20150243385A1
公开(公告)日：2015-08-27
申请号：US14620465
申请日：2015-02-12
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
IPC: G21C15/18
Abstract: A passively-cooled spent nuclear fuel pool system and method therefor. In one embodiment, the invention can be 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 in the body of liquid water that heats the body of liquid water; a lid covering the spent nuclear fuel pool to create a hermetically sealed vapor space between the surface level of the body of liquid water and the lid; and a passive heat exchange sub-system fluidly coupled to the vapor space, the passive heat exchange sub-system configured to: (1) receive water vapor from the vapor space; (2) remove thermal energy from the received water vapor, thereby condensing the water vapor to form a condensed water vapor; and (3) return the condensed water vapor to the body of liquid water.
Abstract translation: 一种被动冷却的废核燃料池系统及其方法。 在一个实施例中，本发明可以是被动冷却的废核燃料池系统，包括：废核燃料池，其包括具有表面水平的液体水体，浸没在液体水体中的至少一个废核燃料棒， 加热液体水体; 覆盖废核燃料池的盖子，以在液体水体的表面水平与盖子之间产生气密密封的蒸汽空间; 被动热交换子系统，被动热交换子系统被配置为：（1）从所述蒸汽空间接收水蒸汽; （2）从接收到的水蒸气中除去热能，从而冷凝水蒸汽，形成冷凝水蒸气; 和（3）将冷凝水蒸汽返回到液态水体内。
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公开(公告)号：US11935663B2
公开(公告)日：2024-03-19
申请号：US17081753
申请日：2020-10-27
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
IPC: G21C7/12 , G21C7/10 , G21C7/117 , G21C9/004 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/10 , G21D1/00
CPC classification number: G21C7/12 , G21C7/10 , G21C7/117 , G21C9/004 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/10 , G21D1/00 , G21D1/006 , Y02E30/30
Abstract: 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.
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Patent Agency Ranking
36.发明授权公开(公告)号：US11901088B2
公开(公告)日：2024-02-13
申请号：US17088815
申请日：2020-11-04
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Gerald Leo Rajkumar
IPC: G21C15/243 , G21C7/32 , G21C15/26 , G21D1/00 , G21C13/073
CPC classification number: G21C15/243 , G21C7/32 , G21C15/26 , G21C13/073 , G21D1/00 , G21D1/006 , Y02E30/30
Abstract: 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.
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公开(公告)号：US11120920B2
公开(公告)日：2021-09-14
申请号：US16682495
申请日：2019-11-13
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Gearald Leo Rajkumar
IPC: G21C15/18 , G21C15/14 , F22B1/02 , G21C13/04 , G21C15/22 , G21C15/26 , G21D1/00 , G21C15/257 , G21C13/032
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.
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公开(公告)号：US11094421B2
公开(公告)日：2021-08-17
申请号：US16744144
申请日：2020-01-15
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
Abstract: 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.
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公开(公告)号：US20200176137A1
公开(公告)日：2020-06-04
申请号：US16710048
申请日：2019-12-11
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
Abstract: 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.
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公开(公告)号：US10580539B2
公开(公告)日：2020-03-03
申请号：US15715631
申请日：2017-09-26
Applicant: SMR INVENTEC, LLC
Inventor： Krishna P. Singh , Indresh Rampall , Joseph Gerald Leo Rajkumar
IPC: G21C15/24 , G21C13/02 , G21C15/243 , G21C9/04
Abstract: 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.
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