公开(公告)号：US20110064180A1

公开(公告)日：2011-03-17

申请号：US12872155

申请日：2010-08-31

申请人： Hirokazu AKATSUKA ,  Toshihiro Kodama

发明人： Hirokazu AKATSUKA ,  Toshihiro Kodama

IPC分类号： G21C7/12

CPC分类号： G21C19/105 ,  G21C7/113

摘要： A control rod grasped by a hook of a grasping equipment is moved down and is positioned at an upper end of a hollow piston of a control rod drive mechanism (CRD) in a state that the control rod is fully withdrawn from a core. Furthermore, the hook is inserted into an opening of a handle of the control rod. The hook is lifted up so as to make contact with the handle. The control rod grasped by the grasping equipment is rotated by a grasping equipment rotation apparatus. A state that gaps formed between joint convexities in a coupling socket of the control rod are positioned right above coupling spud convexities of the hollow piston occurs. At this time, the control rod falls by its own weight and the coupling spud convexities pass through the gaps. A grasping equipment movement apparatus suppresses the falling speed of the control rod. The control rod is rotated at 90° and the control rod and CRD are connected. The time required for connecting the control rod and the hollow piston of the control rod drive mechanism can be shortened even further.

摘要翻译： 在控制棒从芯部完全取出的状态下，由把持装置的钩把持的控制杆向下移动并且位于控制棒驱动机构（CRD）的中空活塞的上端。 此外，将钩插入控制棒的把手的开口中。 钩子被提起以与手柄接触。 由把持装置抓住的控制杆通过把持装置旋转装置旋转。 发生在控制棒的联接插座中的接合凸部之间形成的间隙位于紧邻中空活塞的联轴器凸起之后的状态。 此时，控制棒由自身的重量下降，并且连接的凸起凸出通过间隙。 抓握装置移动装置抑制控制棒的下降速度。 控制杆旋转90°，控制杆和CRD相连。 控制杆驱动机构的控制杆和中空活塞连接所需的时间可以进一步缩短。

公开(公告)号：US07907695B2

公开(公告)日：2011-03-15

申请号：US11680072

申请日：2007-02-28

申请人： Atsushi Watanabe ,  Yoichi Wada ,  Makoto Nagase ,  Kazushige Ishida ,  Hideyuki Hosokawa ,  Fumihito Hirokawa ,  Masaaki Tsubaki ,  Shiro Takahashi

发明人： Atsushi Watanabe ,  Yoichi Wada ,  Makoto Nagase ,  Kazushige Ishida ,  Hideyuki Hosokawa ,  Fumihito Hirokawa ,  Masaaki Tsubaki ,  Shiro Takahashi

IPC分类号： G21C3/56

CPC分类号： G21C1/084 ,  G21C15/00 ,  G21Y2002/402 ,  G21Y2004/30 ,  Y02E30/31

摘要： A natural circulation boiling water reactor provides to a chimney with a plurality of tubes. That is to say, each of the plurality of tubes partitions the coolant flow path above a core. Thus, unlike the conventional natural circulation boiling water reactor providing the flow path partition wall grid in which the plate members are made integral by welding and coolant flow paths are partitioned, the chimney of the natural circulation boiling water reactor can reduce the number of welded portions because the edges of the four corners of each flow path do not need to be welded. The natural circulation boiling water reactor can avoid removal as a single unit, as in the case of the flow path partition wall grid in the conventional natural circulation boiling water reactor, by detaching each tube. The chimney can be easily detached from the reactor pressure vessel.

摘要翻译： 自然循环沸水反应器提供给具有多个管的烟囱。 也就是说，多个管中的每一个将冷却剂流动路径分隔在核心上方。 因此，与传统的自然循环沸水反应器不同，通过焊接使板构件成为一体的流路分隔壁网格，并且冷却剂流动路径被分隔，自然循环沸水反应器的烟囱可以减少焊接部分的数量 因为每个流路的四个角的边缘不需要焊接。 自然循环沸水反应堆可以避免作为单一单元的去除，如在传统的自然循环沸水反应器中的流路分隔壁网格的情况下，通过分离每个管。 烟囱可以容易地与反应堆压力容器分离。

公开(公告)号：US07876872B2

公开(公告)日：2011-01-25

申请号：US11678753

申请日：2007-02-26

申请人： Koichi Sato ,  Shin Hasegawa

发明人： Koichi Sato ,  Shin Hasegawa

IPC分类号： G21C7/06

CPC分类号： G21C1/084 ,  G21C7/08 ,  G21D3/08 ,  G21Y2002/207 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

摘要： In the present invention, a reactor power control apparatus of a natural circulation reactor comprises a reactor pressure vessel which circulates cooling water using the density difference of the coolant inside, a feed water pipe which is connected to the reactor pressure vessel and supplies cooling water, a power control section which controls the reactor power using a control rod. The feed water pipe has an ultrasonic thermometer sensor. Driving of the control rod is controlled by the power control section based on the feed water temperature detected by the feed water thermometer. The reactor power control apparatus can detect the temperature of the feed water and perform drive control of the control rod preferentially, and obtain stable reactor power.

摘要翻译： 在本发明中，天然循环反应器的反应堆功率控制装置包括使用冷却剂内部的密度差循环冷却水的反应堆压力容器，连接到反应堆压力容器并供给冷却水的给水管， 功率控制部，其使用控制棒来控制反应堆功率。 给水管具有超声波温度计传感器。 控制棒的驱动由功率控制部根据给水温度计检测到的给水温度进行控制。 反应堆功率控制装置可以检测给水温度，优先进行控制棒的驱动控制，获得稳定的反应堆功率。

公开(公告)号：US20110005288A1

公开(公告)日：2011-01-13

申请号：US12830169

申请日：2010-07-02

申请人： Yuji MATSUI ,  Masahiro Tooma ,  Atsushi Baba ,  Kouichi Kurosawa ,  Fujio Yoshikubo

发明人： Yuji MATSUI ,  Masahiro Tooma ,  Atsushi Baba ,  Kouichi Kurosawa ,  Fujio Yoshikubo

IPC分类号： B21D26/02

CPC分类号： C21D7/06 ,  C21D11/00

摘要： A high-pressure water jet is injected from a nozzle scanned and a shock wave generated due to the collapse of bubbles included in the water jet is impacted on a WJP execution object. Tensile residual stress close to the surface of the WJP execution object is improved to compressive residual stress. The shock wave is detected by a pressure sensor and a shock wave generation frequency is obtained. Whether the obtained shock wave generation frequency is larger than a set value or not is decided. When the shock wave generation frequency is larger than the set value, a high-pressure pump is stopped and the injection of the water jet from the nozzle is stopped. When the shock wave generation frequency is equal to or smaller than the set value, the operation condition of the high-pressure pump is changed. The pressure of the water jet injected from the nozzle is increased and the WJP is executed for a part of the WJP execution object where the shock wave generation frequency is equal to or smaller than the set value. Improvement effect of the residual stress of the WJP execution object can be confirmed more accurately.

摘要翻译： 从扫描的喷嘴喷射高压水射流，并且由于包含在水射流中的气泡的崩溃而产生的冲击波被冲击到WJP执行对象上。 靠近WJP执行物体表面的拉伸残余应力提高到压缩残余应力。 通过压力传感器检测冲击波，获得冲击波产生频率。 确定获得的冲击波产生频率是否大于设定值。 当冲击波产生频率大于设定值时，停止高压泵并停止喷嘴的喷射。 当冲击波产生频率等于或小于设定值时，改变高压泵的运行状态。 从喷嘴喷射的喷水的压力增加，对于冲击波产生频率等于或小于设定值的WJP执行对象的一部分执行WJP。 可以更准确地确认WJP执行对象的残余应力的改善效果。

公开(公告)号：US07869557B2

公开(公告)日：2011-01-11

申请号：US12354925

申请日：2009-01-16

申请人： Kazushige Ishida ,  Yoichi Wada ,  Makoto Nagase ,  Masahiko Tachibana ,  Masao Endo ,  Motomasa Fuse ,  Naoshi Usui ,  Motohiro Aizawa

发明人： Kazushige Ishida ,  Yoichi Wada ,  Makoto Nagase ,  Masahiko Tachibana ,  Masao Endo ,  Motomasa Fuse ,  Naoshi Usui ,  Motohiro Aizawa

IPC分类号： G21C9/00

CPC分类号： G21C17/0225

摘要： The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.

摘要翻译： 本发明的目的是提供一种减轻反应堆结构材料的应力腐蚀开裂的方法，其可以抑制主蒸汽管线剂量率的上升而没有二次效应，例如放射性钴-60浓度的升高 等等在反应堆水中。 将氢和含有负氧化数的氮（例如肼）的还原氮化合物注入沸水核电厂的核心水中。 通过将含有负氧化数的氮的还原性氮化合物注入芯水中，可以缓解反应器结构材料的应力腐蚀开裂，而不会发生诸如钴-60等的浓度升高的副反应。

公开(公告)号：US07860206B2

公开(公告)日：2010-12-28

申请号：US11657459

申请日：2007-01-25

申请人： Atsushi Fushimi ,  Setsuo Arita ,  Kazuhiko Ishiii ,  Yoshihiko Ishii ,  Shin Hasegawa ,  Atsutoshi Mizuide

发明人： Atsushi Fushimi ,  Setsuo Arita ,  Kazuhiko Ishiii ,  Yoshihiko Ishii ,  Shin Hasegawa ,  Atsutoshi Mizuide

IPC分类号： G21C7/36

CPC分类号： G21C1/084 ,  G21C7/36 ,  G21D3/08 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

摘要： In order to provide a reactor power control apparatus which can maintain a stable water level when reactivity control based on control rod operation and water level adjustment is performed, this invention comprises a turbine control which calculates the load set error signal from the error between the set target generator power value and the generator power that was fed back and outputs to the turbine control apparatus; control rod control in the natural circulation boiling water reactor which calculates the control rod operation signal and outputs it to the control rod drive control apparatus; water level control inside the natural circulation boiling water reactor which calculates the water level set signal and outputs it to the feed water control apparatus; and the switch determining device which selectively outputs one of the control rod control and water level control based on the generator power that was fed back, the reactor power and water level, as well as switching rules and determination values.

摘要翻译： 为了提供一种在基于控制杆操作和水位调节的反应性控制时可以保持稳定的水位的反应堆功率控制装置，本发明包括一个涡轮机控制装置，该装置根据装置的误差计算负载设定误差信号 目标发电机功率值和反馈并输出到涡轮机控制装置的发电机功率; 控制棒控制在自然循环沸水反应堆中，计算控制棒的运行信号，并将其输出到控制棒驱动控制装置; 自然循环沸水反应堆内的水位控制，其计算水位设定信号并输出​​给给水控制装置; 以及切换判定装置，其基于反馈的发电机功率，反应堆功率和水位以及切换规则和判定值选择性地输出控制棒控制和水位控制中的一个。

公开(公告)号：US07844024B2

公开(公告)日：2010-11-30

申请号：US12364556

申请日：2009-02-03

申请人： Hideyuki Hosokawa ,  Makoto Nagase ,  Kazushige Ishida ,  Yoichi Wada ,  Naoshi Usui ,  Motohiro Aizawa ,  Motomasa Fuse

发明人： Hideyuki Hosokawa ,  Makoto Nagase ,  Kazushige Ishida ,  Yoichi Wada ,  Naoshi Usui ,  Motohiro Aizawa ,  Motomasa Fuse

IPC分类号： G21C9/00

CPC分类号： G21C19/42 ,  G21C17/0225 ,  G21F9/06 ,  G21F9/12 ,  G21F9/28

摘要： A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.

摘要翻译： 一种抑制放射性核素在核电厂部件上沉积的方法包括通过使包含铁（II）离子的第一化学品，用于氧化铁（II）离子的第二种化学品与铁（III）离子）接触来形成铁氧体膜，以及 第三种化学品，用于在去除在金属表面形成的污染物的净化步骤的净化步骤的整理阶段中将含有第一和第二化学品的混合物的处理溶液的pH调节至5.5至9.0的金属构件表面 构成核电站的成员，并且通过铁氧体膜抑制放射性核素在金属构件上的沉积。

公开(公告)号：US20100226541A1

公开(公告)日：2010-09-09

申请号：US12707091

申请日：2010-02-17

申请人： Ryosuke KOBAYASHI ,  Satoshi OKADA ,  Masahiro TOOMA ,  Yutaka KOMETANI ,  Yosuke TAKATORI ,  Mitsuru ODAKURA ,  Kojirou KODAIRA

发明人： Ryosuke KOBAYASHI ,  Satoshi OKADA ,  Masahiro TOOMA ,  Yutaka KOMETANI ,  Yosuke TAKATORI ,  Mitsuru ODAKURA ,  Kojirou KODAIRA

IPC分类号： G06T7/00 ,  G01C3/08

CPC分类号： G21C17/013 ,  G06T7/77 ,  G06T2207/30164 ,  G06T2207/30244 ,  G06T2207/30252

摘要： An object of the invention is to provide a system for detecting the position of an underwater vehicle that enables an improvement in the accuracy of detecting the position of the underwater vehicle.The position detection system comprises: a pressure sensor 18 that detects the vertical position of an underwater vehicle 9; a range sensor unit 23 that detects the relative distances of the underwater vehicle 9 from its surrounding structures; a measurement image acquisition unit 36 that acquires a measurement image of the horizontal plane in which the relative distances have been detected; an image storage unit 34 that stores images, each of which has at least one pixel to which horizontal position information is attached and is the image data representing the outer shapes of the structures in a given horizontal plane; an image selector 35 that selects, based on the vertical position of the underwater vehicle 9, one of the stored images that corresponds to the horizontal plane in which the relative distances have been detected; a corresponding-area identification unit 37 that identifies the area in the selected image that corresponds to the measurement image by performing map matching; and horizontal position calculator 38 that identifies, from the corresponding area in the selected image identified by the corresponding-area identification unit 37, the pixel that corresponds to the position at which the relative distances have been detected and calculates the horizontal position of the underwater vehicle.

摘要翻译： 本发明的目的是提供一种用于检测水下车辆的位置的系统，其能够提高检测水下航行器的位置的精度。 位置检测系统包括：检测水下航行器9的垂直位置的压力传感器18; 距离传感器单元23，其检测水下航行器9与其周围结构的相对距离; 测量图像获取单元36，其获取已经检测到相对距离的水平面的测量图像; 存储图像的图像存储单元34，每个图像具有附加有水平位置信息的至少一个像素，并且是表示给定水平面中的结构的外部形状的图像数据; 基于水下航行器9的垂直位置选择与已经检测到相对距离的水平面相对应的所存储的图像之一的图像选择器35; 对应区域识别单元37，其通过执行地图匹配来识别与测量图像相对应的所选图像中的区域; 和水平位置计算器38，其从相应区域识别单元37识别的所选择的图像中的相应区域识别与已经检测到相对距离的位置相对应的像素，并计算水下航行器的水平位置 。

公开(公告)号：US20090141847A1

公开(公告)日：2009-06-04

申请号：US12324936

申请日：2008-11-28

申请人： Tetsushi HINO ,  Masao CHAKI ,  Motoo AOYAMA ,  Takeshi MITSUYASU ,  Yoshihiko ISHII

发明人： Tetsushi HINO ,  Masao CHAKI ,  Motoo AOYAMA ,  Takeshi MITSUYASU ,  Yoshihiko ISHII

IPC分类号： G21D3/10 ,  G21C7/08 ,  G21C7/32 ,  G21C7/00

CPC分类号： G21C7/08 ,  G21C7/32 ,  G21D3/10 ,  Y02E30/39

摘要： An method for operating a nuclear power generation plant, comprising the steps of: forming a plurality of control rod patterns by operating a plurality of control rods during a first period of one operation cycle of a reactor including said first period before a point of time when all control rods are completely withdrawn from a core of said reactor and a core flow rate reaches firstly a set core flow rate, and a second period after said point of time, controlling stepwise at least once a temperature of feed water supplied to said reactor based on a different set feed water temperature during a period included in said first period for operating said reactor with a formed same control rod pattern, and continuing feed water temperature control based on said set feed water temperature until said core flow rate reaches a set core flow rate set based on said set feed water temperature.

摘要翻译： 一种用于操作核发电厂的方法，包括以下步骤：通过在包括所述第一时段的电抗器的一个操作周期的第一周期期间操作多个控制棒来形成多个控制棒图案， 所有控制棒从所述反应器的核心完全取出，并且芯流速率首先达到设定的核心流速，并且在所述时间点之后的第二时间段内，逐步控制供应到所述反应器的给水温度至少一次 在包括在用于以所形成的相同控制杆模式操作所述反应器的所述第一时段期间的不同设定进料水温度下，以及基于所述设定的给水温度继续供水温度控制，直到所述芯流量达到设定的芯流量 基于所述设定的给水温度设定速率。

公开(公告)号：US20090041174A1

公开(公告)日：2009-02-12

申请号：US12186560

申请日：2008-08-06

申请人： Takeshi MITSUYASU ,  Motoo AOYAMA ,  Kazuya ISHII ,  Masao CHAKI

发明人： Takeshi MITSUYASU ,  Motoo AOYAMA ,  Kazuya ISHII ,  Masao CHAKI

IPC分类号： G21C15/06

CPC分类号： G21C3/322 ,  G21C15/02 ,  Y02E30/38

摘要： A reactor core, comprising:an outermost region; a core region surrounded by said outermost region; a plurality of fuel support members, each of which is disposed at a lower end portion of said outermost region and said core region; and a plurality of fuel assemblies loaded in said outermost region and said core region and supported by said fuel support members,wherein a plurality of fuel assemblies disposed in said core region include a plurality of first fuel assemblies, each of which is inserted into a first coolant passage which is formed in said fuel support member and has a first resistor having an opening, and a plurality of second fuel assemblies, each of which is individually inserted into each of second coolant passage which is formed in said fuel support member and has a second resistor having an opening and a larger pressure loss than that of said first resistor; and,four fuel assemblies, each of which is adjacent to each of four lateral sides of each of a plurality of first fuel assemblies, include either three or four second fuel assemblies.

摘要翻译： 一种反应堆芯，包括：最外区; 由所述最外区域包围的芯区域; 多个燃料支撑构件，每个燃料支撑构件设置在所述最外区域的下端部分和所述芯区域; 以及多个燃料组件，其装载在所述最外区域和所述芯区域中并由所述燃料支撑构件支撑，其中设置在所述芯区域中的多个燃料组件包括多个第一燃料组件，每个第一燃料组件插入第一燃料组件 冷却剂通道，其形成在所述燃料支撑构件中并且具有具有开口的第一电阻器，以及多个第二燃料组件，每个第二燃料组件分别插入形成在所述燃料支撑构件中的每个第二冷却剂通道中，并且具有 第二电阻器具有比所述第一电阻器的开口和更大的压力损失; 并且四个燃料组件中的每一个与多个第一燃料组件中的每一个的四个侧面中的每一个相邻，包括三个或四个第二燃料组件。