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31. 发明授权

US10720249B2 Passive reactor cooling system 有权
公开(公告)号：US10720249B2
公开(公告)日：2020-07-21
申请号：US15419227
申请日：2017-01-30
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21C13/02 , G21C15/12 , G21D1/00 , G21C9/004
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.

32. 发明授权

US10115487B2 Shutdown system for a nuclear steam supply system 有权
公开(公告)号：US10115487B2
公开(公告)日：2018-10-30
申请号：US14433394
申请日：2013-10-04
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21D3/14 , F22B1/02 , G21C1/32 , G21C15/00 , G21D1/00 , G21D1/04
摘要： 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 hydraulic-ally 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 tun extracts heat from and cools the primary coolant.

33. 发明授权

US10102936B2 Nuclear stream supply system 有权
公开(公告)号：US10102936B2
公开(公告)日：2018-10-16
申请号：US14620390
申请日：2015-02-12
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21D1/00 , G21D1/04 , G21C15/24 , G21C15/00 , G21C1/32 , F22B1/02 , F01K5/02
摘要： 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.

34. 发明授权

US10008296B2 Passively-cooled spent nuclear fuel pool system 有权
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
IPC分类号： G21C15/18 , G21C19/07 , G21C13/02 , G21C19/04 , G21C11/00
CPC分类号： G21C15/18 , G21C11/00 , G21C13/02 , G21C19/04 , G21C19/07 , Y02E30/40
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.

35. 发明授权

US09786394B2 Component cooling water system for nuclear power plant 有权
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.

36. 发明授权

US09786393B2 Passive reactor containment protection system 有权
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
IPC分类号： G21C15/12 , G21C9/00 , G21C9/004 , G21C13/02 , G21C15/18 , G21C15/26
CPC分类号： G21C15/12 , G21C9/00 , G21C9/004 , G21C13/02 , G21C15/18 , G21C15/26 , Y02E30/40
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.

37. 发明授权

US09496057B2 Fail-safe control rod drive system for nuclear reactor 有权
标题翻译：核反应堆故障安全控制棒驱动系统
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
发明人： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
IPC分类号： G21C7/12 , G21C9/02
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。

38. 发明申请

US20150325318A1 FAIL-SAFE CONTROL ROD DRIVE SYSTEM FOR NUCLEAR REACTOR 有权
标题翻译：用于核反应堆的失效安全控制杆驱动系统
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
发明人： Krishna P. Singh , Patrick Ingravallo , Leyland Vann
IPC分类号： G21C7/12 , G21C9/02
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。

39. 发明申请

US20210142920A1 NUCLEAR STEAM SUPPLY AND START-UP SYSTEM, PASSIVELY-COOLED SPENT NUCLEAR FUEL POOL SYSTEM AND METHOD THEREFOR, COMPONENT COOLING WATER SYSTEM FOR NUCLEAR POWER PLANT, PASSIVE REACTOR COOLING SYSTEM, STEAM GENERATOR FOR NUCLEAR STEAM SUPPLY SYSTEM 有权
公开(公告)号：US20210142920A1
公开(公告)日：2021-05-13
申请号：US17088815
申请日：2020-11-04
申请人： SMR Inventec, LLC
发明人： Krishna P. SINGH , Joseph Gerald Leo RAJKUMAR
IPC分类号： G21D1/00
摘要： A nuclear steam supply system having a start-up sub-system for heating a primary coolant. The nuclear steam supply system comprises a reactor vessel with core comprising nuclear fuel, and steam generating vessel fluidly coupled to the reactor vessel. A primary coolant loop formed within the reactor vessel and the steam generating vessel circulates primary coolant through the loop. A steam supply start-up sub-system is fluidly coupled to the primary coolant loop. The start-up sub-system is configured and operable to: (1) extract and 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 back into the primary coolant loop.

40. 发明申请

US20210050122A1 NUCLEAR REACTOR SYSTEM HAVING NATURAL CIRCULATION OF PRIMARY COOLANT 有权
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
发明人： Krishna P. Singh , P. Stephan Anton , Ranga Nadig , Indresh Rampall
IPC分类号： G21C15/26 , G21C1/08 , G21C7/32 , G21C13/04 , G21C15/12 , G21D1/00
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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