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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
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.
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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
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.
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公开(公告)号：US20180277264A1
公开(公告)日：2018-09-27
申请号：US15996868
申请日：2018-06-04
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
摘要： 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.
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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
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.
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公开(公告)号：US20170133112A1
公开(公告)日：2017-05-11
申请号：US15413770
申请日：2017-01-24
申请人： SMR Inventec, LLC
CPC分类号： G21C15/26 , G21C1/086 , G21C7/32 , G21C13/04 , G21C15/12 , G21D1/006 , Y02E30/32 , Y02E30/39
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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6.发明申请NUCLEAR FUEL CORE, NUCLEAR FUEL CARTRIDGE, AND METHODS OF FUELING AND/OR DEFUELING A NUCLEAR REACTOR 有权核燃料核，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
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。
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公开(公告)号：US20210050122A1
公开(公告)日：2021-02-18
申请号：US16941133
申请日：2020-07-28
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 sub-system 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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公开(公告)号：US10665354B2
公开(公告)日：2020-05-26
申请号：US15901249
申请日：2018-02-21
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 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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公开(公告)号：US20200098483A1
公开(公告)日：2020-03-26
申请号：US16682495
申请日：2019-11-13
申请人： SMR Inventec, LLC
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.
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公开(公告)号：US09852820B2
公开(公告)日：2017-12-26
申请号：US14397135
申请日：2013-04-25
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
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.
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