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公开(公告)号：US20150287483A1
公开(公告)日：2015-10-08
申请号：US14713093
申请日：2015-05-15
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
IPC: G21C15/18
Abstract: A passively-cooled spent nuclear fuel pool system in one embodiment includes a containment vessel comprising a thermally conductive shell and an annular reservoir surrounding the shell that holds a liquid coolant forming a heat sink. A spent fuel pool is disposed inside the containment vessel and includes a body of water in contact with a first peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The first peripheral sidewall of the spent fuel pool is formed by a portion of the shell of the containment vessel adjacent to the fuel pool, thereby defining a shared common heat transfer wall. The heat transfer wall operates to transfer heat from the body of water in the spent fuel pool to the heat sink to cool the body of water. The heat transfer wall comprises metal in one embodiment.
Abstract translation: 在一个实施例中，被动冷却的废核燃料池系统包括容纳容器，其包括导热壳体和围绕壳体的环形储存器，其保持形成散热器的液体冷却剂。 废燃料池设置在安全壳内，并且包括与燃料池的第一外围侧壁接触的水体。 淹没在水体中的至少一个废核燃料棒加热水。 废燃料池的第一周边侧壁由邻近燃料池的容纳容器的壳体的一部分形成，从而限定共用的共同传热壁。 传热壁用于将热量从乏燃料池中的水体转移到散热器以冷却水体。 在一个实施例中，传热壁包括金属。
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公开(公告)号：US20150243388A1
公开(公告)日：2015-08-27
申请号：US14620390
申请日：2015-02-12
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
CPC classification number: G21D1/006 , F01K5/02 , F22B1/023 , G21C1/32 , G21C15/00 , G21C15/24 , G21D1/04 , Y02E30/40
Abstract: A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) 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 into the primary coolant loop.
Abstract translation: 具有用于加热主冷却剂的启动子系统的核蒸汽供应系统。 在一个实施例中，本发明可以是核蒸汽供应系统，其包括：具有内部空腔的反应堆容器，包括设置在内部空腔内的核燃料的反应堆堆芯; 与反应器容器流体耦合的蒸汽发生容器; 形成在反应器容器和蒸汽发生容器内的主冷却剂回路，主冷却剂回路中的主要冷却剂; 所述启动子系统被配置为：（1）从所述主冷却剂回路接收所述主冷却剂的一部分;以及启动子系统，其与所述主冷却剂回路流体耦合。 （2）加热主冷却剂的部分以形成主冷却剂的加热部分; 和（3）将主冷却剂的加热部分注入主冷却剂回路中。
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公开(公告)号：US20150170772A1
公开(公告)日：2015-06-18
申请号：US14423149
申请日：2013-08-21
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
CPC classification number: G21C15/18 , G21C9/012 , G21C11/02 , G21C11/088 , G21C13/02 , G21C15/12 , G21C15/26 , G21C19/07 , G21D1/04 , Y02E30/40
Abstract: A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped
Abstract translation: 核电厂组件冷却水系统。 在一个实施例中，系统包括容纳核反应堆的内部容纳容器和外部容纳外壳结构。 在容纳容器和容纳外壳结构之间形成环形储水器，其提供用于耗散热能的散热器。 提供了一种无壳式热交换器，其具有浸没在保持在环形储水器内的水中的暴露的管束。 来自植物的部件冷却水流过管束，并通过将热量传递给环形储水器来冷却。 在一个非限制性实施例中，管束可以是U形的
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公开(公告)号：US20150085965A1
公开(公告)日：2015-03-26
申请号：US14398946
申请日：2013-05-06
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
IPC: G21D1/00
CPC classification number: G21D1/006 , G21C15/243 , G21Y2002/40 , G21Y2002/501 , Y02E30/40
Abstract: A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity.
Abstract translation: 核蒸汽供应系统包括具有中心轴线的内腔的细长反应器容器，具有设置在内部空腔内的核燃料的反应堆核心和具有至少一个热交换器部分的蒸汽发生容器，所述蒸汽发生容器流体流动 耦合到反应堆容器。 反应堆容器包括具有上凸缘部分和具有头部凸缘部分的头部的壳体。 上凸缘部分联接到头凸缘部分，其中上凸缘部分延伸到内腔中，并且头凸缘部分从内腔向外延伸。
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公开(公告)号：US11205521B2
公开(公告)日：2021-12-21
申请号：US15927284
申请日：2018-03-21
Applicant: SMR Inventec, LLC
Inventor： Thomas Marcille , Joseph Rajkumar
Abstract: A fuel core for a nuclear reactor in one embodiment includes an upper internals unit and a lower internals unit comprising nuclear fuel assemblies. The assembled fuel core includes an upper core plate, a lower core plate, and a plurality of channel boxes extending therebetween. Each channel box comprises a plurality of outer walls and inner walls collectively defining a longitudinally-extending interior channels or cells having a transverse cross sectional area configured for holding no more than a single nuclear fuel assembly in some embodiments. A cylindrical reflector circumferentially surrounds channel boxes and is engaged at opposing ends by the upper and lower core plates. Adjacent cells within each channel box are formed on opposite sides of inner walls such that the cells are separated from each other by the inner walls alone without any water gaps therebetween which benefits neutronics for some small modular reactor designs.
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Patent Agency Ranking
公开(公告)号：US11031146B2
公开(公告)日：2021-06-08
申请号：US16126100
申请日：2018-09-10
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
Abstract: A method for heating primary coolant in a nuclear supply system in one embodiment includes filling a primary coolant loop within a reactor vessel and a steam generating vessel that are fluidly coupled together with a primary coolant, drawing a portion of the primary coolant from the primary coolant loop and into a start-up sub-system, heating the portion of the primary coolant to form a heated portion of the primary coolant, and injecting the heated portion of the primary coolant back into the primary coolant loop. The primary coolant may be heated to a no-load operating temperature.
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公开(公告)号：US10672523B2
公开(公告)日：2020-06-02
申请号：US15729376
申请日：2017-10-10
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
Abstract: A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.
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公开(公告)号：US10665357B2
公开(公告)日：2020-05-26
申请号：US15859934
申请日：2018-01-02
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
IPC: G21D1/00 , G21C15/243 , G21C13/073
Abstract: A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. The flanges have a space saving design which are configured to minimize outward extension from the cavity while still providing desired leak protection at the interface between the shell and the head.
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公开(公告)号：US20190019588A1
公开(公告)日：2019-01-17
申请号：US16139043
申请日：2018-09-23
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
Abstract: A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulically interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel. A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in turn extracts heat from and cools the primary coolant.
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公开(公告)号：US10096389B2
公开(公告)日：2018-10-09
申请号：US14289545
申请日：2014-05-28
Applicant: SMR Inventec, LLC
Inventor： Krishna P. Singh , Joseph Rajkumar
Abstract: 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.
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