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1. 发明申请

US20180019026A1 STATIONARY ISOLATED ROD COUPLINGS FOR USE IN A NUCLEAR REACTOR CONTROL ROD DRIVE 审中-公开
公开(公告)号：US20180019026A1
公开(公告)日：2018-01-18
申请号：US15640428
申请日：2017-06-30
申请人： GE-Hitachi Nuclear Energy Americas LLC
发明人： Kenneth A. Morgan , David L. Major , Randy M. Brown
IPC分类号： G21C7/14 , H02K9/19 , G21C15/02 , H02K41/02 , G21C13/02
CPC分类号： G21C7/14 , F16B2001/0035 , G21C7/12 , G21C13/02 , G21C15/02 , G21C17/10 , H01F7/08 , H02K7/116 , H02K9/19 , H02K41/02 , H02K41/031 , Y02E30/39
摘要： Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate the magnetic fields across a full stroke length of the control element in the reactor. A closed coolant loop may cool the induction coils, which may be in a vacuum outside the isolation barrier. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Methods of operation include selectively energizing or de-energizing induction coils to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.

2. 发明申请

US20170263344A1 SERVICING A NUCLEAR REACTOR MODULE 审中-公开
公开(公告)号：US20170263344A1
公开(公告)日：2017-09-14
申请号：US15609997
申请日：2017-05-31
申请人： NuScale Power, LLC
发明人： Ross Snuggerud
IPC分类号： G21C21/02 , G21C17/10 , G21C19/20
CPC分类号： G21C19/207 , B66C13/44 , B66C13/46 , G21C1/322 , G21C17/10 , G21D1/00 , Y02E30/40 , Y10T29/49721 , Y10T29/53539
摘要： A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

3. 发明授权

US09721683B2 Wireless transmission of nuclear instrumentation signals 有权
公开(公告)号：US09721683B2
公开(公告)日：2017-08-01
申请号：US14057346
申请日：2013-10-18
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： Richard W. Morris
IPC分类号： G21C17/00 , G21C17/10 , G21D7/04
CPC分类号： G21C17/00 , G21C17/10 , G21D7/04 , H04Q9/00
摘要： A system for monitoring a condition of a nuclear reactor pressure vessel disposed in a radioactive environment includes an instrument structured to monitor a condition of the nuclear reactor pressure vessel; a powered wireless transmitting modem disposed in the radioactive environment, the wireless transmitting modem being electrically coupled to the instrument; a receiving modem disposed in the line of sight of the transmitting modem, the receiving modem being in wireless communication with the transmitting modem; and a signal processing unit electrically coupled to the receiving modem, the signal processing unit being structured to determine the condition of the nuclear reactor pressure vessel from the instrument. The transmitting modem is powered by a thermocouple disposed in or on the reactor pressure vessel.

4. 发明申请

US20160155519A1 SPOT WELDING GUN AND WELDING METHOD FOR THE NUCLEAR FUEL SKELETON 有权
标题翻译：点焊焊枪和焊接方法为核燃料骨架
公开(公告)号：US20160155519A1
公开(公告)日：2016-06-02
申请号：US14643188
申请日：2015-03-10
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Hyung Sup Kim , Soon Gi Guk , Se Ick Son , Byung Tak Kim
IPC分类号： G21C3/334 , B23K11/00
CPC分类号： G21C3/334 , B23K11/002 , B23K11/115 , G21C3/3424 , G21C17/10 , G21C21/00 , Y02E30/40
摘要： A spot welding device for a nuclear fuel skeleton, which is assembled by spot-welding guide tubes for control rods and a instrumentation tube for measuring a state of an inside of a nuclear reactor to a spacer grid that has a plurality of cells formed in a thickness direction of a plate-shaped frame for inserting fuel rods, has a instrumentation tube hole formed at a center, and has four guide tube holes formed symmetrically above and below the instrumentation tube hole. The device includes: a welding gun including: a body, a first holder and a second holder extending from a side of the body and having respective electrodes facing each other at ends, respectively, and a driving unit disposed on the body and adjusting a distance between the electrodes; and a robot connected to the welding gun and having a rotary joint for rotating the welding gun.
摘要翻译：用于核燃料骨架的点焊装置，其通过用于控制棒的点焊引导管和用于测量核反应堆内部状态的仪表管组装成具有形成在多个单元中的多个单元的间隔栅格用于插入燃料棒的板状框架的厚度方向具有形成在中心的仪表管孔，并且在仪表管孔的上方和下方对称地形成有四个导管孔。该装置包括：焊枪，包括：主体，第一保持器和第二保持器，其分别从主体的一侧延伸并具有分别在端部彼此面对的电极;以及驱动单元，其布置在主体上并调节距离在电极之间; 以及连接到焊枪的机器人，并具有用于旋转焊枪的旋转接头。

5. 发明申请

US20160111173A1 GAMMA-RAY SENSING PROBE USING CERENKOV EFFECT AND SYSTEM FOR IDENTIFYING BURNUP OF SPENT NUCLEAR FUEL ASSEMBLY USING THE SAME 审中-公开
标题翻译：使用CERENKOV效应的GAMMA-RAY感测探头和识别燃烧核燃料组件的系统
公开(公告)号：US20160111173A1
公开(公告)日：2016-04-21
申请号：US14895467
申请日：2013-06-20
申请人： SOONCHUNHYANG UNIVERSITY INDUSTRY ACADEMY COOPERATION FOUNDATION
发明人： Byung Gi Park , Bong Soo Lee , Kyoung Won Jang , Wook Jae Yoo , Sang Hun Shin
IPC分类号： G21C17/10 , G01T1/167 , G01T1/22
CPC分类号： G21C17/10 , G01T1/167 , G01T1/22
摘要： Provided are a gamma-ray sensing probe using the Cerenkov effect, and a system for identifying the burnup of a spent nuclear fuel assembly using the gamma-ray sensing probes, wherein the system is established using the gamma-ray sensing probe including: an optical fiber reacting to gamma rays coming from the spent nuclear fuel assembly by the Cerenkov effect and emitting light by itself; a scatterer surrounding the optical fiber to increase light emitting efficiency of the optical fiber by the Cerenkov effect; and a collimator configured to surround the scatterer and composed of a shielding material, the collimator having a slit groove which is open in one direction, whereby the burnup of the spent nuclear fuel assembly can be accurately determined.
摘要翻译：提供了使用Cerenkov效应的伽马射线感测探头和用于识别使用伽马射线感测探头的乏核燃料组件的燃耗的系统，其中使用伽马射线感测探针建立该系统，该系统包括：光学纤维与来自废核燃料组件的伽马射线通过Cerenkov效应反应并自身发射光; 围绕光纤的散射体，以通过Cerenkov效应提高光纤的发光效率; 以及准直器，被配置为围绕所述散射体并且由屏蔽材料构成，所述准直器具有沿一个方向开放的狭缝槽，从而可以准确地确定废核燃料组件的燃耗。

6. 发明申请

US20150332795A1 Rod Control and Information System, Control Rod Individual Controller, and Test Method for Rod Control and Information System 审中-公开
标题翻译：杆控制和信息系统，控制杆单独控制器和杆控制和信息系统的测试方法
公开(公告)号：US20150332795A1
公开(公告)日：2015-11-19
申请号：US14697746
申请日：2015-04-28
申请人： Hitachi, Ltd.
发明人： Soichiro KODAMA , Satoru AKASAKA , Satoru NISHIMURA
IPC分类号： G21C17/10 , G21C7/12
CPC分类号： G21C17/10 , G21C7/12 , G21D3/001 , Y02E30/39
摘要： The invention includes conducting efficiently a functional verification test of a rod control and information system as a whole and of control rod on-site transmission devices only, the system performing and monitoring insertion and extraction of control rods to and from a nuclear reactor. Each on-site transmission device in the system includes a control rod drive controller and multiple control rod individual controllers each incorporating beforehand a software simulator that calculates position change of the control rods corresponding to a control rod drive command input to the individual controller via the control rod drive controller. During the test, a software simulator activation signal is issued to activate the software simulator calculating a simulated control rod position and outputting the position as a control rod position signal for use in determining the integrity of the on-site transmission devices and that of the system.
摘要翻译：本发明包括有效地执行杆控制和信息系统作为一个整体的功能验证测试，以及仅控制棒现场传动装置的系统，该系统执行和监视控制棒的进出核反应堆的插入和抽出。系统中的每个现场传动装置包括控制杆驱动控制器和多个控制棒单独的控制器，每个控制杆各自预先包含一个软件模拟器，该软件模拟器通过控制器计算控制杆的位置变化，该控制杆对应于控制杆驱动命令输入到各个控制器杆驱动控制器。在测试期间，发出软件模拟器激活信号以激活软件模拟器，计算模拟控制棒的位置并输出该位置作为控制杆位置信号，以用于确定现场传动装置和系统的完整性。

7. 发明授权

US09177676B2 Nuclear reactor power monitor 有权
标题翻译：核反应堆功率监视器
公开(公告)号：US09177676B2
公开(公告)日：2015-11-03
申请号：US13697950
申请日：2011-05-11
申请人： Yutaka Takeuchi , Hiroshi Ono , Kazuki Yano
发明人： Yutaka Takeuchi , Hiroshi Ono , Kazuki Yano
IPC分类号： G21C17/00 , G21C17/10 , G21D3/00
CPC分类号： G21C17/00 , G21C17/10 , G21D3/001 , G21D2003/005 , Y02E30/40
摘要： Provide a nuclear reactor power monitoring technology for enhancing the monitoring accuracy and reliability in nuclear thermal hydraulic stability.A power monitor 30 includes a first calculation unit 42,52 configured to calculate a first stability index based on time series data indicating power oscillation in nuclear instrumentation signals outputted from a plurality of nuclear instrumentation detectors 31; a first determination unit 44,53 configured to compare the first stability index and a first reference value and determine whether nuclear thermal hydraulic stability of the reactor core is stable or deteriorated; a second calculation unit 46,54 configured to calculate a second stability index of the reactor core based on the time series data when the deteriorated state is determined in the first determination unit 44,53; and a second determination unit 47,55 configured to compare the second stability index and a second reference value and determine whether to perform suppressing operation of the power oscillation.
摘要翻译：提供核反应堆功率监测技术，提高核热液压稳定性的监测精度和可靠性。功率监视器30包括第一计算单元42,52，其被配置为基于表示从多个核仪器检测器31输出的核仪器信号中的功率振荡的时间序列数据来计算第一稳定性指标; 第一确定单元44,53，被配置为比较第一稳定性指数和第一参考值，并确定反应堆堆芯的核热液压稳定性是否稳定或劣化; 第二计算单元46,54，被配置为当在第一确定单元44,53中确定恶化状态时，基于时间序列数据计算反应堆堆芯的第二稳定性指数; 以及第二确定单元47,55，被配置为比较第二稳定性指标和第二参考值，并确定是否执行功率振荡的抑制操作。

8. 发明授权

US09082518B2 Nuclear reactor vibration monitoring apparatus and method of monitoring nuclear reactor vibration 有权
标题翻译：核反应堆振动监测装置及核反应堆振动监测方法
公开(公告)号：US09082518B2
公开(公告)日：2015-07-14
申请号：US13672189
申请日：2012-11-08
申请人： Hitachi-GE Nuclear Energy, Ltd.
发明人： Masahiro Hiratsuka , Atsushi Baba , Masahiro Koike , Taro Ikezumi , Minoru Ootaka
IPC分类号： G21C17/003 , G21C15/25 , G21C17/10 , G01N29/07 , G01N29/46
CPC分类号： G21C17/003 , G01N29/07 , G01N29/46 , G01N2291/044 , G21C15/25 , G21C17/10 , Y02E30/31
摘要： Vibration of a jet pump installed in a reactor pressure vessel of a boiling water reactor is monitored. Ultrasonic waves are transmitted from an ultrasonic sensor installed on an outer surface of the reactor pressure vessel toward a throat and a diffuser of the jet pump. When the ultrasonic waves reach respective outer surfaces of the throat and diffuser, reflected waves are generated at the respective outer surfaces. The ultrasonic sensor receives those reflected waves. The ultrasonic signal process section obtains a distance in the horizontal direction between the throat and the diffuser based on a time difference of the reflected waves reflected from respective reflection surfaces of the throat and diffuser and a sound speed in reactor water in the neighborhood of the throat and diffuser. A relative vibration is obtained based on the change with time of the distance.
摘要翻译：监测安装在沸水反应堆的反应堆压力容器中的喷射泵的振动。超声波从安装在反应堆压力容器的外表面上的超声波传感器传送到喷射泵的喉部和扩散器。当超声波到达喉部和扩散器的相应外表面时，在相应的外表面产生反射波。超声波传感器接收那些反射波。超声波信号处理部基于从喉部和扩散器的各反射面反射的反射波的时间差和咽喉附近的反应堆水中的声速来获得喉部与扩散器之间的水平方向的距离和扩散器。基于距离随时间的变化获得相对振动。

9. 发明授权

US08873694B2 Primary neutron source multiplier assembly 有权
标题翻译：初级中子源倍增器组件
公开(公告)号：US08873694B2
公开(公告)日：2014-10-28
申请号：US12899596
申请日：2010-10-07
申请人： David L. Stucker
发明人： David L. Stucker
IPC分类号： G21G4/02 , G21C3/326 , G21C17/10
CPC分类号： G21G4/02 , G21C3/326 , G21C17/10 , Y02E30/38
摘要： A neutron emitting assembly, which is useful in nuclear reactors and other industrial applications, is made of a major amount of beryllium encapsulating a minor amount of 252Cf, which can be placed in a capsule having end plugs and a holding spring.
摘要翻译：在核反应堆和其他工业应用中有用的中子发射组件由主要量的铍包裹少量的252Cf制成，其可以放置在具有端塞和保持弹簧的胶囊中。

10. 发明申请

US20140185728A1 SYSTEMS AND METHODS FOR DISPOSING OF ONE OR MORE RADIOACTIVE COMPONENTS FROM NUCLEAR REACTORS OF NUCLEAR PLANTS 审中-公开
标题翻译：从核工厂的核反应堆处理一种或多种放射性成分的系统和方法
公开(公告)号：US20140185728A1
公开(公告)日：2014-07-03
申请号：US13729646
申请日：2012-12-28
申请人： Michael Joseph GUNDRUM , Chris SWICK , Joseph CAPOBIANCO
发明人： Michael Joseph GUNDRUM , Chris SWICK , Joseph CAPOBIANCO
IPC分类号： G21C19/32
CPC分类号： G21C19/32 , G21C17/10 , G21C19/20
摘要： A system for disposing of one or more radioactive components from a nuclear reactor may include a first receptacle configured to receive the one or more radioactive components, a frame configured to support the first receptacle in the nuclear reactor, and a device configured to separate the one or more radioactive components into two or more portions during lowering of the one or more radioactive components into the first receptacle. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components, and moving the assembled system to an area of a reactor core. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components in an area of a reactor core.
摘要翻译：用于处置来自核反应堆的一种或多种放射性成分的系统可以包括构造成接收一种或多种放射性组分的第一容器，被配置为支撑核反应堆中的第一容器的框架，以及被配置为将一个或更多的放射性成分在将一种或多种放射性组分降入第一容器期间分成两部分或更多部分。用于从核反应堆处置一种或多种放射性成分的方法可包括组装用于处置一种或多种放射性组分的系统，以及将组装的系统移动到反应堆芯的区域。从核反应堆处理一种或多种放射性成分的方法可包括组装用于处理反应堆核心区域中的一种或多种放射性组分的系统。

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