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31.
公开(公告)号:US20190139657A1
公开(公告)日:2019-05-09
申请号:US15807049
申请日:2017-11-08
IPC分类号: G21C15/18 , G21C15/12 , G21C13/024 , G21D1/00
摘要: A floating nuclear power reactor is provided and includes a barge floating in a tank filled with water. The reactor includes a self-cooling containment structure and an emergency heat exchange system.
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公开(公告)号:US20190057789A1
公开(公告)日:2019-02-21
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 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.
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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
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.
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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
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.
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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: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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37.
公开(公告)号:US09969889B2
公开(公告)日:2018-05-15
申请号:US14692339
申请日:2015-04-21
发明人: Masato Okamura , Osamu Shibasaki , Koji Negishi , Seiji Yamamoto , Hajime Hirasawa , Kenji Yamazaki , Tetsuji Kaneko
IPC分类号: C09D5/08 , C23F11/18 , C23F11/08 , F01D5/28 , F16L58/08 , F22B37/02 , F22B37/10 , C08K3/22 , C08K3/26 , C08K5/098 , G21D1/00
CPC分类号: C09D5/08 , C08K3/22 , C08K3/26 , C08K5/098 , C08K2003/221 , C23F11/08 , C23F11/18 , C23F11/185 , F01D5/288 , F05D2220/31 , F16L58/08 , F22B37/025 , F22B37/108 , G21D1/00 , Y10T428/273
摘要: The present invention provides a corrosion-resistant structure for a high-temperature water system comprising: a structural material 1; and a corrosion-resistant film 3 formed from a substance containing at least one of La and Y deposited on a surface in a side that comes in contact with a cooling water 4, of the structural material 1 which constitutes the high-temperature water system that passes a cooling water 4 of high temperature therein. Due to above construction, there can be provided the corrosion-resistant structure and a corrosion-preventing method capable of operating a plant without conducting a water chemistry control of cooling water by injecting chemicals.
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公开(公告)号:US20180053571A1
公开(公告)日:2018-02-22
申请号:US15689724
申请日:2017-08-29
申请人: BWXT mPower, Inc.
发明人: Thomas G. Graham
CPC分类号: G21C15/182 , G21C1/09 , G21C9/012 , G21C15/185 , G21D1/00 , G21D3/06 , Y02E30/32
摘要: In conjunction with a pressurized water reactor (PWR) and a pressurizer configured to control pressure in the reactor pressure vessel, a decay heat removal system comprises a pressurized passive condenser, a turbine-driven pump connected to suction water from at least one water source into the reactor pressure vessel; and steam piping configured to deliver steam from the pressurizer to the turbine to operate the pump and to discharge the delivered steam into the pressurized passive condenser. The pump and turbine may be mounted on a common shaft via which the turbine drives the pump. The at least one water source may include a refueling water storage tank (RWST) and/or the pressurized passive condenser. A pressurizer power operated relief valve may control discharge of a portion of the delivered steam bypassing the turbine into the pressurized passive condenser to control pressure in the pressurizer.
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公开(公告)号:US20180033505A1
公开(公告)日:2018-02-01
申请号:US15445376
申请日:2017-02-28
发明人: Sung Ho PARK , Jong Min KIM , Kyu Wan KIM
CPC分类号: G21D1/006 , F16T1/00 , F22B21/04 , G21C1/322 , G21C15/12 , G21C15/16 , G21Y2004/305 , Y02E30/40
摘要: In an externally integrated steam generator type small modular reactor, a steam generator is arranged along the circumference of a reactor vessel cylindrical shell, and a steam drum is arranged along the circumference of the steam generator. The small modular reactor includes: a nuclear reactor including a hemispherical upper head, the reactor vessel cylindrical shell coupled to the upper head and extending downward from the upper head in a cylindrical shape, and a hemispherical lower head provided on a lower portion of the reactor vessel cylindrical shell, wherein a core is placed in the nuclear reactor; the steam generator surrounding all around the reactor vessel cylindrical shell and including a first penetration hole communicating with an inside of the nuclear reactor; and the steam drum surrounding the circumference of the steam generator and including a second penetration hole communicating with an inside of the steam generator.
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公开(公告)号:US09859026B2
公开(公告)日:2018-01-02
申请号:US14408483
申请日:2013-06-19
IPC分类号: G21C15/02 , C21D8/10 , C22C19/05 , C22C38/00 , C22F1/00 , C22F1/02 , C22F1/10 , G21D1/00 , C22C38/02 , C22C38/04 , C22C38/06 , C22C38/42 , C22C38/50 , C21D1/26 , C21D6/00 , C21D9/08 , C22C30/00 , C22C38/40
CPC分类号: G21C15/02 , C21D1/26 , C21D6/004 , C21D8/10 , C21D8/105 , C21D9/08 , C22C19/05 , C22C19/058 , C22C30/00 , C22C38/00 , C22C38/02 , C22C38/04 , C22C38/06 , C22C38/40 , C22C38/42 , C22C38/50 , C22F1/00 , C22F1/02 , C22F1/10 , G21D1/006 , Y02E30/40
摘要: An austenitic alloy tube subjected to a cold working and an annealing heat treatment contains C: 0.01% to 0.15%, Cr: 10.0% to 40.0%, Ni: 8.0% to 80.0%, in mass %, and has a metallographic structure satisfying the following Expressions (i) to (iii). R≦f1 (i) R=I220/I111 (ii) f1=0.28×(F1118.0/(F1118.0+0.358.0)) (iii) Where, in the above Expressions, R is a ratio of an integrated intensity of {220} to an integrated intensity of {111} on a surface layer which is measured by a grazing incidence X-ray diffraction method, I220 is the integrated intensity of {220}, I111 is the integrated intensity of {111}, and F111 is full width of half maximum of {111} on the surface layer which is measured by the grazing incidence X-ray diffraction method.
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