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公开(公告)号：US09721681B2
公开(公告)日：2017-08-01
申请号：US13863659
申请日：2013-04-16
摘要： An integral pressurized water reactor (PWR) comprises: a cylindrical pressure vessel including an upper vessel section and a lower vessel section joined by a mid-flange; a cylindrical central riser disposed concentrically inside the cylindrical pressure vessel and including an upper riser section disposed in the upper vessel section and a lower riser section disposed in the lower vessel section; steam generators disposed inside the cylindrical pressure vessel in the upper vessel section; a reactor core comprising fissile material disposed inside the cylindrical pressure vessel in the lower vessel section; and control rod drive mechanism (CRDM) units disposed inside the cylindrical pressure vessel above the reactor core and in the lower vessel section. There is no vertical overlap between the steam generators and the CRDM units.
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公开(公告)号：US20150194226A1
公开(公告)日：2015-07-09
申请号：US14170727
申请日：2014-02-03
发明人： Robert P Martin , Michael J Edwards
IPC分类号： G21C11/00
摘要： A nuclear reactor is surrounded by a reactor radiological containment structure. A spent fuel pool is adjacent to and outside of the reactor radiological containment structure. The spent fuel pool may also be contained in its own radiological containment structure. A valved steam pipe runs from the reactor containment structure into the spent fuel pool. During a reactor containment overpressure event, a valve on the steam pipe is opened to allow steam from the reactor containment structure to discharge into (e.g. sparge into) the spent fuel pool. In an alternative embodiment suitable for use in a two-pack nuclear power plant, steam pipes connect the reactor radiological containment structures of the two nuclear reactors, and isolation valves on the steam pipes are opened in response to an overpressure condition in one reactor containment structure in order to discharge steam into the other reactor containment structure.
摘要翻译： 一个核反应堆被一个反应堆放射性遏制结构所包围。 废燃料池与反应堆放射性容纳结构相邻并且在其外部。 乏燃料池也可能包含在其自身的放射性遏制结构中。 有阀门的蒸汽管道从反应堆容纳结构延伸到乏燃料池中。 在反应堆容纳超压事件期间，蒸汽管上的阀打开以允许来自反应堆容纳结构的蒸汽排放到（例如喷射）废燃料池中。 在适用于双组件核电站的替代实施例中，蒸汽管连接两个核反应堆的反应堆放射性容纳结构，并且响应于一个反应堆容纳结构中的超压状况而打开蒸汽管上的隔离阀 以将蒸汽排放到另一个反应堆容纳结构中。
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公开(公告)号：US20140133619A1
公开(公告)日：2014-05-15
申请号：US13863901
申请日：2013-04-16
发明人： Vince J. Bilovsky
IPC分类号： G21C7/00
CPC分类号： G21C7/00 , G21C1/322 , G21C3/326 , G21C3/3262 , G21C5/18 , G21C7/04 , G21C7/08 , G21D3/08 , Y02E30/32 , Y02E30/38 , Y02E30/39
摘要： A pressurized water reactor (PWR) includes a pressure vessel containing a nuclear reactor core immersed in primary coolant water, control rod assemblies (CRA's), and control rod drive mechanisms (CRDM's) operating the CRA's. The reactor core has axially varying 235U enrichment and/or axially varying burnable poison concentration. A CRDM controller controls the CRA's over a burn-up cycle that does not include fuel assembly shuffling and is divided into a plurality of burn-up intervals. The CRDM controller is configured to, for each burn up interval: position the CRA's in accordance with a CRA pattern defining a set of fixed positions for the CRA's except for a sub-set of CRA's designated by the CRA pattern as floating CRA's, and control power level of the PWR by adjusting the floating CRA's without not adjusting the CRA's not designated as floating CRA's. The primary coolant water optionally does not contain soluble neutron poison.
摘要翻译： 加压水反应堆（PWR）包括一个压力容器，该压力容器含有沉积在一次冷却水中的核反应堆堆芯，控制杆组件（CRA）和操作CRA的控制杆驱动机构（CRDM）。 反应堆芯具有轴向变化的235U富集和/或轴向变化的可燃毒物浓度。 CRDM控制器在不包括燃料组装洗牌的燃尽循环中控制CRA，并且被分为多个燃烧间隔。 CRDM控制器被配置为对于每个燃烧间隔：将CRA定位为根据CRA模式定位CRA模式，该CRA模式为CRA定义一组固定位置，除了由CRA模式指定的CRA子集作为浮动CRA，并且控制 通过调整浮动CRA而不调整未指定为浮动CRA的CRA，PWR的功率级别。 主冷却水任选地不含有可溶性中子毒素。
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公开(公告)号：US20130272471A1
公开(公告)日：2013-10-17
申请号：US13861085
申请日：2013-04-11
发明人： Thomas G. GRAHAM
IPC分类号： G21C9/00
摘要： A nuclear power plant comprises a pressurized water reactor (PWR) and a steam generator driving a turbine driving an electric generator. A condenser condenses steam after flowing through the turbine. Responsive to a station blackout, the nuclear power plant is electrically isolated and a bypass valve is opened to convey bypass steam flow from the steam generator to the condenser without flowing through the turbine. The thermal power output of the PWR is gradually reduced over the transition time interval. After opening, the bypass valve is gradually closed over the transition time interval. A supplemental bypass valve may also be opened responsive to the station blackout to convey supplemental bypass steam flow from the steam generator to a feedwater system supplying secondary coolant feedwater to the steam generator. The supplemental bypass steam flow does not flow through the turbine and does not flow through the condenser.
摘要翻译： 核电站包括压水反应堆（PWR）和驱动发电机的涡轮的蒸汽发生器。 冷凝器在流经涡轮后冷凝蒸汽。 响应于停电站，核电站是电隔离的，并且旁路阀打开以将旁路蒸汽流从蒸汽发生器传送到冷凝器而不流过涡轮机。 在过渡时间间隔内，PWR的热功率输出逐渐减小。 打开后，旁通阀在过渡时间间隔内逐渐关闭。 补充旁通阀还可以响应于站停电而被打开，以将补充的旁路蒸汽流从蒸汽发生器传送到向蒸汽发生器供应二次冷却剂给水的给水系统。 补充旁路蒸汽流不流过涡轮机，并且不流过冷凝器。
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公开(公告)号：US20180261338A1
公开(公告)日：2018-09-13
申请号：US14215119
申请日：2014-03-17
发明人： Scott J Shargots
摘要： A control rod guide frame has a central passage of constant cross-section as a function of position along a central axis that passes through the central passage. The central passage is sized and shaped to guide a traveling assembly including at least one control rod as it moves along the central axis. The control rod guide frame comprises at least two radial guide frame sections secured around and defining the central passage. Each radial guide frame section may comprise an extruded radial guide frame section, which may be made of extruded steel. The central passage may include control rod guidance channels parallel the central axis and machined into the extruded radial guide frame sections. The at least two radial guide frame sections may be interchangeable. In some embodiments the at least two radial guide frame sections consist of between four and eight radial guide frame sections.
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6.发明授权公开(公告)号：US09875817B2
公开(公告)日：2018-01-23
申请号：US14299268
申请日：2014-06-09
发明人： Tyler A Edwards , Michael J Edwards
IPC分类号： G21C13/024 , G21C5/10 , G21C9/016 , G21C15/18
CPC分类号： G21C5/10 , G21C9/016 , G21C13/024 , G21C15/18 , Y02E30/40
摘要： A nuclear reactor including a lateral seismic restraint with a vertically oriented pin attached to the lower vessel head and a mating pin socket attached to the floor. Thermally insulating materials are disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head.
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公开(公告)号：US09754688B2
公开(公告)日：2017-09-05
申请号：US13861480
申请日：2013-04-12
发明人： Matthew W Ales , Scott Shargots
摘要： A pressure vessel comprises an upper vessel section and a lower vessel section. A nuclear reactor core comprises fissile material contained in a containing structure and disposed in the lower vessel section. Upper internals are disposed in the lower vessel section above the nuclear reactor core. The upper internals include at least guide frames and internal control rod drive mechanisms (CRDMs) with CRDM motors mounted on a suspended support assembly including a plurality of hanger plates connected by tie rods. The plurality of hanger plates includes a lowermost hanger plate having alignment features configured to align the upper internals with the containing structure that contains the nuclear reactor core.
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8.发明申请INTEGRAL ISOLATION VALVE SYSTEMS AND METHODS OF OPERATING SAME FOR LOSS OF COOLANT ACCIDENT (LOCA) PROTECTION 审中-公开集成隔离阀系统及其相应的冷却系统故障（LOCA）保护操作方法公开(公告)号：US20160027535A1
公开(公告)日：2016-01-28
申请号：US14337268
申请日：2014-07-22
发明人： David J. KANUCH , Paul P. DiFILIPO
IPC分类号： G21C15/18
摘要： A nuclear reactor includes a nuclear reactor core comprising fissile material disposed in a reactor pressure vessel having vessel penetrations that exclusively carry flow into the nuclear reactor and at least one vessel penetration that carries flow out of the nuclear reactor. An integral isolation valve (IIV) system includes passive IIVs each comprising a check valve built into a forged flange and not including an actuator, and one or more active IIVs each comprising an active valve built into a forged flange and including an actuator. Each vessel penetration exclusively carrying flow into the nuclear reactor is protected by a passive IIV whose forged flange is directly connected to the vessel penetration. Each vessel penetration carrying flow out of the nuclear reactor is protected by an active IIV whose forged flange is directly connected to the vessel penetration. Each active valve may be a normally closed valve.
摘要翻译： 核反应堆包括核反应堆核心，其包括布置在反应堆压力容器中的易裂变材料，其具有专门携带流入核反应堆的容器穿透和至少一个载体流出核反应堆的容器穿透。 一体式隔离阀（IIV）系统包括无源IIV，每个都包括内置于锻造法兰中的止回阀，不包括致动器，以及一个或多个主动IIV，每个活塞IIV包括内置于锻造法兰中并包括致动器的主动阀。 每个容器穿透仅通过流入核反应堆的流体被被动式IIV保护，其被伪造的法兰直接连接到容器穿透。 从核反应堆流出的每个容器渗透物被活化的IIV保护，其中锻造法兰直接连接到容器穿透。 每个主动阀可以是常闭阀。
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公开(公告)号：US20150357061A1
公开(公告)日：2015-12-10
申请号：US14299424
申请日：2014-06-09
发明人： Matthew W. ALES , Mark C. GODDEN
CPC分类号： G21C15/182 , B23K31/02 , F04D7/08 , F16F15/30 , G21C1/322 , G21C15/243 , G21C21/02 , Y02E30/40 , Y02E70/30 , Y10T29/49828
摘要： A nuclear reactor coolant pump (RCP) comprises a stator and a rotating assembly including a rotor, an impeller, and a flywheel configured to rotate about an axis of rotation in response to the stator being electrically energized. The flywheel comprises a first material (such as stainless steel) and has a plurality of mutually parallel tubular openings filled with a second material that is denser than the first material (such as tungsten or tungsten alloy). In some embodiments the mutually parallel tubular openings are cylindrical openings, and are filled with the second material comprising cylindrical rods. In a nuclear reactor including a reactor pressure vessel and a nuclear reactor core comprising fissile 235U disposed in the reactor pressure vessel, the RCP is suitably disposed on or in the reactor pressure vessel with the impeller of the RCP arranged to engage coolant water disposed in the reactor pressure vessel.
摘要翻译： 核反应堆冷却剂泵（RCP）包括定子和旋转组件，旋转组件包括转子，叶轮和飞轮，其构造成响应于定子被电通电而围绕旋转轴线旋转。 飞轮包括第一材料（例如不锈钢），并且具有填充有比第一材料（例如钨或钨合金）更致密的第二材料的多个相互平行的管状开口。 在一些实施例中，相互平行的管状开口是圆柱形开口，并且填充有包括圆柱形杆的第二材料。 在包括反应堆压力容器的核反应堆和设置在反应堆压力容器中的裂变235U的核反应堆核心中，RCP适当地设置在反应堆压力容器中或反应堆压力容器中，其中RCP的叶轮布置成接合设置在反应堆压力容器中的冷却水 反应堆压力容器。
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