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    Nozzle repairing method and nuclear reactor vessel
    2.
    发明授权
    Nozzle repairing method and nuclear reactor vessel 有权
    喷嘴修复方法和核反应堆容器

    公开(公告)号：US09375813B2

    公开(公告)日：2016-06-28

    申请号：US13853610

    申请日：2013-03-29

    申请人： MITSUBISHI HEAVY INDUSTRIES, LTD.

    发明人： Takeshi Yamamoto ,  Tomochika Hamamoto ,  Nobuyuki Hori ,  Tsuyoshi Nishimura ,  Hideshi Sakashita

    IPC分类号： G21C9/00 ,  B23P6/04 ,  G21C13/02 ,  G21C13/036 ,  G21C17/017 ,  G21C19/20 ,  G21C5/00

    CPC分类号： B23P6/04 ,  G21C5/00 ,  G21C13/02 ,  G21C13/036 ,  G21C17/017 ,  G21C19/207 ,  Y02E30/40 ,  Y10T29/49734 ,  Y10T29/49737

    摘要： It is possible to improve the workability and the stress corrosion resistance by easily performing a repairing operation in a nozzle repairing method and a nuclear reactor vessel. The repairing method includes: removing a first connection portion ((trepanned portion) 208) with respect to an in-core instrument tube (204) in a groove-welding portion (206); removing the in-core instrument tube (204) from a lower mirror (66); leaving and grooving a second connection portion ((existing welding portion) 211) with respect to the lower mirror (66) in the groove-welding portion (206); inserting a new in-core instrument tube (204A) into an attachment hole (203); and groove-welding (so as to form a new groove-welding portion (213)) the inner side of the lower mirror (66) so as to fix the new in-core instrument tube (204A).

    摘要翻译： 通过在喷嘴修复方法和核反应堆容器中容易进行修理操作，可以提高加工性和耐应力腐蚀性。 所述修复方法包括：相对于槽焊接部分（206）中的核心内仪表管（204）去除第一连接部分（（棘手部分）208）; 从下反射镜（66）移除核心内仪器管（204）; 在凹槽焊接部分（206）中相对于下反射镜（66）留下并切割第二连接部分（（存在的焊接部分）211）; 将新的核心仪器管（204A）插入连接孔（203）中; 以及下反射镜（66）的内侧的沟槽焊接（以形成新的槽焊接部分（213）），以固定新的核心仪表管（204A）。

    Reactor core of liquid metal cooled reactor
    3.
    发明授权
    Reactor core of liquid metal cooled reactor 失效
    液态金属冷却反应堆的反应堆芯

    公开(公告)号：US08711997B2

    公开(公告)日：2014-04-29

    申请号：US13361543

    申请日：2012-01-30

    申请人： Tsugio Yokoyama ,  Hisato Matsumiya ,  Yasushi Tsuboi

    发明人： Tsugio Yokoyama ,  Hisato Matsumiya ,  Yasushi Tsuboi

    IPC分类号： G21C7/06 ,  G21C7/00

    CPC分类号： G21C1/322 ,  G21C1/02 ,  G21C1/32 ,  G21C3/02 ,  G21C5/00 ,  G21C7/04 ,  G21C7/103 ,  G21Y2002/201 ,  G21Y2002/207 ,  G21Y2002/301 ,  G21Y2002/50 ,  G21Y2004/30 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/39

    摘要： A reactor core is immersed in a liquid metal coolant in a core barrel of a liquid metal cooled reactor. The reactor core includes a plurality of fuel assemblies contained in the core barrel, a neutron absorber that absorbs a neutron in the reactor core, and a neutron moderator that moderates a neutron therein so as to control a reactivity of the reactor core. The neutron absorber and the neutron moderator constitute a mixture contained in reactivity control assemblies of the reactor core in the liquid metal coolant prior to immersion of the reactor core. The neutron moderator is composed of zirconium hydride.

    摘要翻译： 将反应堆芯浸入液态金属冷却反应器的芯筒中的液态金属冷却剂中。 反应堆堆芯包括在核心筒中包含的多个燃料组件，吸收反应堆芯中的中子的中子吸收器和缓和其中的中子以控制反应堆芯的反应性的中子减速剂。 中子吸收器和中子慢化剂构成在反应堆芯浸入之前液态金属冷却剂中的反应堆芯的反应性控制组件中所含的混合物。 中子减速剂由氢化锆组成。

    ADVANCED FIRST CORE FUEL ASSEMBLY CONFIGURATION AND METHOD OF IMPLEMENTING THE SAME
    5.
    发明申请
    ADVANCED FIRST CORE FUEL ASSEMBLY CONFIGURATION AND METHOD OF IMPLEMENTING THE SAME 有权
    高级第一核心燃料组件配置及其实施方法

    公开(公告)号：US20120294406A1

    公开(公告)日：2012-11-22

    申请号：US13451050

    申请日：2012-04-19

    申请人： David L. Stucker ,  Robert J. Fetteman ,  Jeffrey L. Bradfute

    发明人： David L. Stucker ,  Robert J. Fetteman ,  Jeffrey L. Bradfute

    IPC分类号： G21C19/00

    CPC分类号： G21C19/205 ,  G21C1/086 ,  G21C3/326 ,  G21C5/00 ,  G21C2003/3265 ,  G21Y2002/201 ,  G21Y2004/403 ,  Y02E30/38

    摘要： An advanced initial core fuel configuration is for improving the fuel management efficiency and thus economics for a nuclear reactor. A method of implementing such an initial core involves providing a plurality of fuel assemblies having different average enrichments of uranium 235 and arranging the fuel assemblies in an initial core configuration structured to emulate a known equilibrium reload cycle core at least in terms of spatial reactivity distribution. The resulting average enrichment within the initial core ranges from below about 1.0 percent weight of uranium 235 to about 5.0 percent weight of uranium 235. An advanced lattice design is also disclosed.

    摘要翻译： 先进的初始核燃料配置是提高燃料管理效率，从而提高核反应堆的经济性。 实现这种初始核心的方法包括提供具有不同的铀235的平均富集度的多个燃料组件，并且将燃料组件布置成至少根据空间反应性分布构造成模拟已知的平衡重载循环核心的初始核心配置。 初始核中的所得平均浓度范围从铀235的约1.0重量％至铀235的约5.0重量％。还公开了先进的晶格设计。

    REACTIVITY CONTROL ROD FOR CORE, CORE OF NUCLEAR REACTOR, NUCLEAR REACTOR AND NUCLEAR POWER PLANT
    6.
    发明申请
    REACTIVITY CONTROL ROD FOR CORE, CORE OF NUCLEAR REACTOR, NUCLEAR REACTOR AND NUCLEAR POWER PLANT 审中-公开
    核反应堆，核反应堆核，核反应堆和核电厂的反应控制线

    公开(公告)号：US20110194664A1

    公开(公告)日：2011-08-11

    申请号：US13006260

    申请日：2011-01-13

    申请人： Tsugio YOKOYAMA ,  Hisato Matsumiya ,  Yasushi Tsuboi

    发明人： Tsugio YOKOYAMA ,  Hisato Matsumiya ,  Yasushi Tsuboi

    IPC分类号： G21C7/06

    CPC分类号： G21C1/322 ,  G21C1/02 ,  G21C1/32 ,  G21C3/02 ,  G21C5/00 ,  G21C7/04 ,  G21C7/103 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/39

    摘要： In a nuclear reactor in which a primary coolant is contained, the primary coolant moves upwardly from the core by an operation thereof. An annular steam generator is arranged in an upper side of the core into which the upwardly moving primary coolant flows and transfers heat in the primary coolant into water therein to generate a steam. A passage structure defines a coolant passage for the primary coolant to an outside of the core. The heat-transferred primary coolant in the annular steam generator flows downwardly in the coolant passage so as to flow into the core, thereby moving upwardly. A reactor vessel is arranged to surround the coolant passage so as to contain the core, the annular steam generator and the passage means therein.

    摘要翻译： 在其中容纳主要冷却剂的核反应堆中，主冷却剂通过其操作从芯向上移动。 环形蒸汽发生器布置在芯的上侧，向上移动的一次冷却剂向其中流动，并将主冷却剂中的热量转移到其中以产生蒸汽。 通道结构将用于主冷却剂的冷却剂通道定义到芯的外部。 环形蒸汽发生器中传热的主要冷却剂在冷却剂通道中向下流动，以便流入核心，从而向上移动。 反应堆容器布置成围绕冷却剂通道以便容纳核心，环形蒸汽发生器和其中的通道装置。

    CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY
    7.
    发明申请
    CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY 有权
    轻水反应堆和燃料组件的核心

    公开(公告)号：US20110164720A1

    公开(公告)日：2011-07-07

    申请号：US12978198

    申请日：2010-12-23

    申请人： Renzo TAKEDA ,  Junichi Miwa ,  Kumiaki Moriya

    发明人： Renzo TAKEDA ,  Junichi Miwa ,  Kumiaki Moriya

    IPC分类号： G21C1/04

    CPC分类号： G21C3/328 ,  G21C1/084 ,  G21C3/42 ,  G21C5/00 ,  G21C5/02 ,  G21C19/44 ,  Y02E30/38 ,  Y02W30/882

    摘要： A core of a light water reactor has a plurality of fuel assemblies. The fuel assemblies include a plurality of fuel rods in which a lower end is supported by a lower tie-plate and an upper end is supported by an upper tie-plate. The fuel rods form plenums above a nuclear fuel material zone and have a neutron absorbing material filling zone under the nuclear fuel material zone. Neutron absorbing members attached to the upper tie-plate are disposed between mutual plenums of the neighboring fuel rods above the nuclear fuel material zone. The neutron absorbing members have a length of 500 mm and are positioned at a distance of 300 mm from the nuclear fuel material zone. Even if the overall core is assumed to become a state of 100% void, no positive reactivity is inserted to the core.

    摘要翻译： 轻水反应堆的核心具有多个燃料组件。 燃料组件包括多个燃料棒，其中下端由下连接板支撑，上端由上连接板支撑。 燃料棒在核燃料材料区之上形成集气室，并在核燃料材料区下方具有中子吸收材料填充区。 附接到上连接板的中子吸收构件设置在核燃料材料区域上方的相邻燃料棒的相互增压室之间。 中子吸收构件具有500mm的长度并且位于与核燃料材料区300mm的距离处。 即使假设整个核心成为100％空白的状态，也不会向核心插入积极的反应性。

    Nuclear Reactor Operation and Simulation
    8.
    发明申请
    Nuclear Reactor Operation and Simulation 有权
    核反应堆运行与模拟

    公开(公告)号：US20110069801A1

    公开(公告)日：2011-03-24

    申请号：US12565402

    申请日：2009-09-23

    申请人： Jon D. McWhirter ,  Charles Whitmer ,  Lowell L. Wood, JR. ,  George B. Zimmerman

    发明人： Jon D. McWhirter ,  Charles Whitmer ,  Lowell L. Wood, JR. ,  George B. Zimmerman

    IPC分类号： G21C17/00

    CPC分类号： G21D3/001 ,  G06F17/5009 ,  G21C1/026 ,  G21C5/00 ,  G21C7/00 ,  G21C17/00 ,  G21D2003/002 ,  Y02E30/34 ,  Y02E30/39

    摘要： Illustrative embodiments provide for the operation and simulation of the operation of fission reactors. Illustrative embodiments and aspects include, without limitation, nuclear fission reactors and reactor modules, including modular nuclear fission reactors and reactor modules, nuclear fission deflagration wave reactors and reactor modules, modular nuclear fission deflagration wave reactors and modules, methods of operating nuclear reactors and modules including the aforementioned, methods of simulating operating nuclear reactors and modules including the aforementioned, and the like.

    摘要翻译： 示例性实施例提供了对裂变反应堆的操作的操作和模拟。 说明性的实施方案和方面包括但不限于核裂变反应堆和反应堆模块，包括模块式核裂变反应堆和反应堆模块，核裂变爆燃波反应堆和反应堆模块，模块式核裂变爆燃波反应堆和模块，运行核反应堆和模块的方法 包括前述的模拟运行的核反应堆的方法和包括上述的模块等。

    REFUELING SUPPORT SYSTEM
    9.
    发明申请
    REFUELING SUPPORT SYSTEM 审中-公开
    补救支持系统

    公开(公告)号：US20090161811A1

    公开(公告)日：2009-06-25

    申请号：US12342298

    申请日：2008-12-23

    申请人： Hitoshi SATO ,  Junichi KOYAMA

    发明人： Hitoshi SATO ,  Junichi KOYAMA

    IPC分类号： G21C19/00

    CPC分类号： G21C5/00 ,  G21C19/205 ,  Y02E30/40

    摘要： Problem: To provide a refueling support system in which fuel transfer procedure establishing operations and associated operations precisely reflecting the fuel burnup conditions can be efficiently performed at the time of scheduled outages at a nuclear power plant.Solution: a reactor core performance calculation means for evaluating neutronic characteristics per fuel assembly from core loading pattern input data of a reactor core before beginning of refueling at the end of a predetermined cycle n and candidate reactor cores at the end of refueling at the beginning of the following cycle n+1 and from core performance calculation results from a process computer;a transfer condition setting means for determining an intermediate fuel loading pattern target which should be realized in the process of refueling from transfer condition input data including Intermediate fuels-to-be-unloaded and transfer priority levels, anda transfer procedure planning means for determining fuel transfer procedures from the neutronic characteristics per fuel assembly which are output from said reactor core performance calculation means and from the Intermediate fuel loading pattern target which is output from said transfer condition setting means are comprised.

    摘要翻译： 问题：提供一个加油支援系统，其中在核电厂预定中断时可以有效地执行燃料转运程序建立操作和精确反映燃料燃耗条件的相关操作。 解决方案：一种反应堆堆芯性能计算装置，用于在预定循环n结束时开始加油之前，从反应堆核心的核心装载模式输入数据中评估每个燃料组件的中子特性，以及在开始时加油结束时的候选反应堆堆芯 以下循环n + 1和来自过程计算机的核心性能计算结果; 转移条件设定装置，用于确定在加油过程中应当从包括中间燃料即将卸载和转移优先级的转移条件输入数据中实现的中间燃料装载模式目标，以及用于确定燃料的转移程序计划装置 包括从所述反应堆堆芯性能计算装置输出的每个燃料组件的中子特性和从所述转移条件设定装置输出的中间燃料装载模式目标的转移程序。