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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
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
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.
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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
申请人： SMR INVENTEC, LLC
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.
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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
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.
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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
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.
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公开(公告)号：US20180068751A1
公开(公告)日：2018-03-08
申请号：US15715631
申请日：2017-09-26
申请人： SMR INVENTEC, LLC
IPC分类号： G21C15/24 , G21C15/243 , G21C13/02 , 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.
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公开(公告)号：US20180047469A1
公开(公告)日：2018-02-15
申请号：US15729376
申请日：2017-10-10
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
CPC分类号： G21C15/12 , G21C9/012 , G21C11/02 , G21C11/088 , G21C13/02 , G21C15/18 , G21C15/26 , G21C19/07 , Y02E30/40
摘要： 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：US20150110236A1
公开(公告)日：2015-04-23
申请号：US14397135
申请日：2013-04-25
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/24
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.
摘要翻译： 一种使用重力驱动的自然循环的初级冷却剂流经流体互连的反应堆容器和蒸汽发生容器的核蒸汽供应系统。 在一个实施例中，蒸汽发生容器包括多个垂直堆叠的热交换器，其可操作以通过利用来自反应堆容器中的核燃料芯的主要冷却剂所获得的热量将二次冷却剂从饱和液体转化为过热蒸汽。 在一些实施例中，二次冷却剂可以是与兰金动力循环涡轮发电机组相关联的工作流体。 蒸汽发生容器和反应堆容器可以各自包括垂直细长的外壳，在一个实施例中，它们以横向相邻的关系排列。 在一个实施例中，反应堆容器和蒸汽发生容器是物理上离散的自支撑结构，其可以物理地位于相同的容纳容器中。
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公开(公告)号：US11289219B2
公开(公告)日：2022-03-29
申请号：US16695102
申请日：2019-11-25
申请人： SMR INVENTEC, LLC
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.
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公开(公告)号：US11031146B2
公开(公告)日：2021-06-08
申请号：US16126100
申请日：2018-09-10
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
摘要： 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：US10726962B2
公开(公告)日：2020-07-28
申请号：US15413770
申请日：2017-01-24
申请人： SMR Inventec, LLC
摘要： A nuclear reactor system that, in one embodiment, utilizes natural circulation to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heat exchange subsystem is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heat exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground.
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