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公开(公告)号：US20180254113A1
公开(公告)日：2018-09-06
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：US10008296B2
公开(公告)日：2018-06-26
申请号：US14713093
申请日：2015-05-15
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 peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The 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：US20180144838A1
公开(公告)日：2018-05-24
申请号：US15859934
申请日：2018-01-02
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21D1/00 , G21C15/243
摘要： 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.
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公开(公告)号：US09786394B2
公开(公告)日：2017-10-10
申请号：US14423149
申请日：2013-08-21
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21C15/12 , G21C15/26 , G21C11/08 , G21D1/04 , G21C9/012 , G21C11/02 , G21C13/02 , G21C19/07
CPC分类号： G21C15/18 , G21C9/012 , G21C11/02 , G21C11/088 , G21C13/02 , G21C15/12 , G21C15/26 , G21C19/07 , G21D1/04 , 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：US09786393B2
公开(公告)日：2017-10-10
申请号：US14403082
申请日：2013-05-21
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh
摘要： A nuclear reactor containment system with passive cooling capabilities. In one embodiment, the system includes an inner containment vessel for housing a nuclear steam supply system and an outer containment enclosure structure. An annular water-filled reservoir may be provided between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy, in the event of a thermal energy release incident inside the containment vessel, the reactor containment system provides passive water and air cooling systems operable to regulate the heat of the containment vessel and the equipment inside. In one embodiment, cooling water makeup to the system is not required to maintain containment vessel and reactor temperatures within acceptable margins.
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公开(公告)号：US20170200515A1
公开(公告)日：2017-07-13
申请号：US15419227
申请日：2017-01-30
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：US09496057B2
公开(公告)日：2016-11-15
申请号：US14417628
申请日：2013-08-05
申请人： SMR Inventec, LLC
CPC分类号： G21C7/14 , G21C7/12 , G21C9/02 , G21Y2004/30 , Y02E30/39
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.
摘要翻译： 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线性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 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：US20160012923A1
公开(公告)日：2016-01-14
申请号：US14771018
申请日：2014-02-27
申请人： SMR INVENTEC, LLC
IPC分类号： G21C15/24 , G21C9/04 , G21C15/243 , G21C13/02
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.
摘要翻译： 在一个实施例中的核反应堆包括具有内腔的圆柱形主体，核燃料芯和设置在空腔中的护罩。 护罩包括内壳，外壳和设置在内壳和外壳之间的多个中间壳。 在内壳和外壳之间形成多个环形腔，其中填充有诸如软化水的初级冷却剂。 冷却剂填充的环形空腔可以在顶部和底部被密封，并且对护罩提供绝缘效果。 在一个实施例中，护罩可以包括多个垂直堆叠的自支撑护罩段，它们联接在一起。
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公开(公告)号：US20150325318A1
公开(公告)日：2015-11-12
申请号：US14417628
申请日：2013-08-05
申请人： SMR Inventec, LLC
CPC分类号： G21C7/14 , G21C7/12 , G21C9/02 , G21Y2004/30 , Y02E30/39
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.
摘要翻译： 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接合的驱动杆并处于适当位置。
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