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公开(公告)号：WO2023026594A1
公开(公告)日：2023-03-02
申请号：PCT/JP2022/019720
申请日：2022-05-09
申请人： 日立ＧＥニュークリア・エナジー株式会社
摘要： 沸騰水型原子炉（１１）は、燃料集合体（２０）の側面を囲むように配置された四角筒状のチャンネルボックス（２２）と、チャンネルボックスの側面上部を支持する円板状の格子板（１７）と、を備えている。格子板（１７）は、チャンネルボックス（２２）の上部が挿入される複数の孔（３３）が設けられた内周部（３０）に対し、外周部の全周又は一部の上面の高さが高い。
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2.发明申请
公开(公告)号：WO2019022640A1
公开(公告)日：2019-01-31
申请号：PCT/RU2018/000478
申请日：2018-07-18
发明人： АФРЕМОВ, Дмитрий Александрович , САФРОНОВ, Денис Викторович , ХИЖНЯК, Евгения Сергеевна , НИКЕЛЬ, Кирилл Альбертович , РОМАНОВА, Наталия Викторовна
IPC分类号： G21C15/00
摘要： Изобретение относится к области ядерной техники и может быть использовано при организации естественной циркуляции жидкометаллического теплоносителя в контуре теплоотвода ядерного реактора на быстрых нейтронах. Для создания движущего напора циркуляции без использования насосного оборудования и обеспечения требуемого направления естественной циркуляции жидкометаллического теплоносителя в контуре теплоотвода ядерного реактора на быстрых нейтронах в отсутствии теплопередачи от реактора перед заполнением трубопроводов и оборудования подъемного и опускного участков контура осуществляют их предварительный электронагрев соответственно до температур T 1 и Т 2 , которые выбирают из условия выполнения неравенства: ρ 1 (Τ 1 ) · g · ΔH 1 > ρ 2 (T 2 ) · g · ΔΗ 2 + ΔΡ, где: ρ 1 (T 1 ) - плотность жидкометаллического теплоносителя при температуре Т 1 трубопроводов и оборудования на подъемном участке; ρ 2 (Т 2 ) - плотность жидкометаллического теплоносителя при температуре Т 2 трубопроводов и оборудования на опускном участке; ΔH 1 — разница высот между входом и выходом подъемного участка; ΔΗ 2 - разница высот между входом и выходом опускного участка; ΔΡ - гидравлическое сопротивление контура; g - ускорение силы тяжести. Запуск циркуляции теплоносителя в контуре и переход в режим естественной циркуляции осуществляют одновременно и до выхода ядерного реактора на номинальные параметры работы путем создания движущего напора циркуляции за счет разницы плотностей p 1 (T 1 ) и ρ 2 (Т 2 ) жидкометаллического теплоносителя соответственно на подъемном и опускном участках контура.
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公开(公告)号：WO2014158377A1
公开(公告)日：2014-10-02
申请号：PCT/US2014/015491
申请日：2014-02-10
CPC分类号： F22B37/483 , F22B37/54 , F28G13/00
摘要： A method of cleaning sludge from the top of tube sheet (34')of a nuclear steam generator (10) includes introducing a moveable suction apparatus (120) having attached vacuum inlets (148), said moveable suction apparatus introduced through handholes (62) in the side of the generator and into either the no tube lane (60) or the circumferential annulus, and sludge vacuuming the top of the tube sheet (34').
摘要翻译： 一种从核蒸汽发生器（10）的管板（34'）的顶部清洗污泥的方法包括引入具有附接真空入口（148）的可移动抽吸装置（120），所述可移动抽吸装置通过手孔（62）引入， 在发动机的侧面并且进入无管道（60）或周向环形空间，并且污泥将管板（34'）的顶部抽真空。
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公开(公告)号：WO2014133658A1
公开(公告)日：2014-09-04
申请号：PCT/US2013/076389
申请日：2013-12-19
发明人： LIAO, Jun , KUCUKBOYACI, Vefa N.
摘要： A passive cooling system of a pressurized water reactor that relies on a depressurization system to reduce the pressure in the reactor vessel in the event of a loss of coolant accident and vent the steam generated by the decay heat of the reactor core in a post loss of coolant accident stage. The depressurization results in a low pressure difference between the reactor vessel and the containment and enables gravity driven cooling system injection into the reactor vessel. The depressurization system includes a flow restrictor within an orifice in the reactor vessel wall that connects to a vent pipe which forms a flow path between the interior of the reactor vessel and the containment atmosphere when a valve within the vent pipe is in an open position. Preferably, the flow restrictor is a venturi that has a gradual contraction and a gradual expansion in the flow path area.
摘要翻译： 压缩水反应堆的被动冷却系统，其依赖于减压系统以在冷却剂事故损失的情况下降低反应堆容器中的压力，并且在反应堆堆芯的后损失中排出由反应堆堆芯的衰变热产生的蒸汽 冷却液事故阶段。 减压导致反应堆容器和容器之间的低压差，并使重力驱动冷却系统注入反应器容器。 减压系统包括在反应堆容器壁中的孔内的限流器，其连接到排气管，该通风管在通气管内的阀处于打开位置时形成反应容器内部和容纳气氛之间的流动路径。 优选地，限流器是文氏管，其在流动通道区域中具有逐渐收缩和逐渐膨胀。
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公开(公告)号：WO2014028630A1
公开(公告)日：2014-02-20
申请号：PCT/US2013/054961
申请日：2013-08-14
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.
摘要翻译： 在一个实施例中，具有用于加热主冷却剂的启动子系统的核蒸汽供应系统，本发明可以是核蒸汽供应系统，其包括： 具有内部空腔的反应器容器，包含设置在所述内部空腔内的核燃料的反应堆堆芯; 与反应器容器流体耦合的蒸汽发生容器; 形成在反应器容器和蒸汽发生容器内的主冷却剂回路，主冷却剂回路中的主要冷却剂; 所述启动子系统被配置为：（1）从所述主冷却剂回路接收所述主冷却剂的一部分;以及启动子系统，其与所述主冷却剂回路流体耦合。 （2）加热主冷却剂的部分以形成主冷却剂的加热部分; 和（3）将主冷却剂的加热部分注入主冷却剂回路中。
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6.发明申请PRESSURIZED WATER REACTOR WITH UPPER VESSEL SECTION PROVIDING BOTH PRESSURE AND FLOW CONTROL 审中-公开具有提供两个压力和流量控制的上部容器部分的增压水反应器
公开(公告)号：WO2013095742A2
公开(公告)日：2013-06-27
申请号：PCT/US2012/057840
申请日：2012-09-28
发明人： SHARGOTS, Scott, J.
CPC分类号： G21C1/32 , F04D13/10 , G21C1/086 , G21C1/09 , G21C15/24 , G21C15/243 , G21C21/00 , G21D1/04 , Y02E30/32 , Y10T29/49236 , Y10T29/49245
摘要： A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.
摘要翻译： 压力水反应堆（PWR）包括垂直圆柱形压力容器，其具有包含核反应堆芯的下部和限定一体式加压器的容器头。 安装在容器头上的反应堆冷却剂泵（RCP）包括压力容器内的叶轮，压力容器外部的泵马达和连接马达和叶轮的垂直驱动轴。 驱动轴不通过整体式加压器。 驱动轴通过压力容器的容器穿透，其至少足够大以使叶轮通过。
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公开(公告)号：WO2012060880A2
公开(公告)日：2012-05-10
申请号：PCT/US2011001856
申请日：2011-11-02
申请人： SEARETE LLC , AHLFELD CHARLES E , BURKE THOMAS M , ELLIS TYLER S , GILLELAND JOHN ROGERS , HEJZLAR JONATAN , HEJZLAR PAVEL , HYDE RODERICK A , MCALEES DAVID G , MCWHIRTER JON DAVID , ODEDRA ASHOK , PETROSKI ROBERT C , TOURAN NICHOLAS W , WALTER JOSHUA C , WEAVER KEVAN D , WEAVER THOMAS ALLAN , WHITMER CHARLES , WOOD LOWELL L JR , ZIMMERMAN GEORGE B
发明人： AHLFELD CHARLES E , BURKE THOMAS M , ELLIS TYLER S , GILLELAND JOHN ROGERS , HEJZLAR JONATAN , HEJZLAR PAVEL , HYDE RODERICK A , MCALEES DAVID G , MCWHIRTER JON DAVID , ODEDRA ASHOK , PETROSKI ROBERT C , TOURAN NICHOLAS W , WALTER JOSHUA C , WEAVER KEVAN D , WEAVER THOMAS ALLAN , WHITMER CHARLES , WOOD LOWELL L JR , ZIMMERMAN GEORGE B
摘要： Disclosed embodiments include nuclear fission reactor cores, nuclear fission reactors, methods of operating a nuclear fission reactor, and methods of managing excess reactivity in a nuclear fission reactor.
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公开(公告)号：WO2012050805A1
公开(公告)日：2012-04-19
申请号：PCT/US2011/053200
申请日：2011-09-26
发明人： LEE, Yu, Chung , CHOI, Joonhyung
IPC分类号： G21C15/00
CPC分类号： G21C3/331 , G21C3/12 , G21C3/3315 , Y02E30/40
摘要： A nuclear fuel assembly having a plurality of multi-leaf hold down spring sets extending from a top nozzle. Each spring set consists of a multiple number of springs leafs in order to provide a large working range of spring deflection. Each spring leaf has a straight, flat base section followed by a straight, flat tapered beam with a secondary spring set having a curvature at its peripheral end.
摘要翻译： 一种核燃料组件，其具有从顶部喷嘴延伸的多个多叶压缩弹簧组。 每个弹簧组由多个弹簧叶组成，以提供弹簧偏转的大的工作范围。 每个弹簧叶片具有直的平坦的基部部分，随后是直的扁平的锥形梁，其二次弹簧组件在其外周端具有曲率。
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公开(公告)号：WO2009055106A2
公开(公告)日：2009-04-30
申请号：PCT/US2008070573
申请日：2008-07-19
申请人： RAMBERG CHARLES
发明人： RAMBERG CHARLES
摘要： Heat from an ex-vessel mass of core material is removed to cooler regions of a containment envelope via liquid and/or vapor phase transport. Various aspects provide for contacting the ex-vessel core material with a material having properties including melting point, boiling point, and condensation kinetics such that condensation of the material in cooler regions of the containment envelope is at least as fast as evaporation of the material due to heat absorption from the core material and associated species.
摘要翻译： 通过液相和/或气相传输将来自外部容器质量的芯材料的热量移除至封闭壳体的较冷区域。 各种方面提供了使外容器芯材料与具有包括熔点，沸点和冷凝动力学性质的材料接触，使得材料在容器封套的较冷区域中的冷凝至少与由于材料蒸发 以加热核心物质和相关物质的吸收。
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公开(公告)号：WO1992015994A1
公开(公告)日：1992-09-17
申请号：PCT/US1991004639
申请日：1991-06-28
IPC分类号： G21C15/00
摘要： A steam separator for a boiling water reactor includes a pressure vessel and a chimney spaced radially inwardly therefrom to define a downcomer therebetween for recirculating water, the chimney being disposed above a reactor core for channeling upwardly therefrom steam voids and water flow. An annular partition wall is spaced radially between the vessel and the chimney to define an annular collection chamber having an inlet for receiving a portion of the steam voids and water flow from the chimney, a steam outlet for discharging the steam voids from the chamber, and a flow outlet for discharging the water flow from the chamber into the downcomer.
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