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11. 发明申请

WO2006081268A2 NEUTRON DETECTOR ASSEMBLY WITH VARIABLE LENGTH RHODIUM EMITTERS 审中-公开
标题翻译： NEUTRON检测器组件与可变长度的RHODIUM发射器
公开(公告)号：WO2006081268A2
公开(公告)日：2006-08-03
申请号：PCT/US2006/002548
申请日：2006-01-24
申请人： FRAMATOME ANP INC. , CHENG, Alexander Y.C.
发明人： CHENG, Alexander Y.C.
IPC分类号： G21C17/00
CPC分类号： G21C17/108 , G21C17/102 , G21Y2002/204 , G21Y2002/301 , G21Y2002/304 , G21Y2002/40 , G21Y2004/30
摘要： A system to measure neutron flux in a nuclear fuel assembly includes at least two detectors placed in a nuclear fuel assembly, each of the detectors having an outer sheath and an inner emitter, the emitter having a structure to accept neutrons and provide an electrical signal, the outer sheath forming an interior volume into which the emitter is placed, an exterior lead, and at least one lead connected to each emitter, the lead transmitting the signal from the emitter to the exterior lead, wherein the at least two detectors are of a different length.
摘要翻译：用于测量核燃料组件中的中子通量的系统包括放置在核燃料组件中的至少两个检测器，每个检测器具有外护套和内部发射器，发射器具有接收中子并提供电信号的结构，所述外护套形成放置发射器的内部容积，外部引线和连接到每个发射器的至少一个引线，所述引线将所述信号从所述发射器传输到所述外部引线，其中所述至少两个检测器为不同长度。

12. 发明申请

WO2006078276A2 PROTECTION OF REACTOR CORES FROM UNSTABLE DENSITY WAVE OSCILLATIONS 审中-公开
标题翻译：从不稳定的密度波振荡的反应器保护
公开(公告)号：WO2006078276A2
公开(公告)日：2006-07-27
申请号：PCT/US2005/014117
申请日：2005-04-21
申请人： FRAMATOME ANP INC. , FARAWILA, Yousef, M. , PRUITT, Douglas, W.
发明人： FARAWILA, Yousef, M. , PRUITT, Douglas, W.
IPC分类号： G21C19/00
CPC分类号： G21C7/36 , G21C7/00 , G21C17/108 , G21D3/12 , G21Y2002/207 , G21Y2002/303 , G21Y2002/306 , G21Y2002/502 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： The present invention provides a method of operating a Boiling Water Reactor, having the steps of analyzing LPRM signals for oscillatory behavior indicative of neutron-flux-coupled density wave oscillations, determining if oscillatory behavior is present in the signals; initiating a reactor protective corrective action if the oscillatory behavior is determined, and in addition, initiating corrective actions if neutron uncoupled oscillations are possible. Detecting the later is performed through analytically determined exclusion zone on the power flow map or by on-line stability calculations for several high power channels.
摘要翻译：本发明提供了一种操作沸水反应堆的方法，具有分析LPRM信号以表示中子 - 通量耦合密度波振荡的振荡特性的步骤，确定信号中是否存在振荡行为; 如果确定了振荡行为，则启动反应堆保护性纠正措施，此外，如果中子非耦合振荡是可能的，则启动纠正措施。通过功率流图上的分析确定的排除区域或通过几个高功率通道的在线稳定性计算来执行后期的检测。

13. 发明申请

WO2006074375A2 SEGMENT MAKE-UP SYSTEM AND METHOD FOR MANUFACTURING NUCLEAR FUEL RODS 审中-公开
标题翻译：部分制造系统和制造核燃料棒的方法
公开(公告)号：WO2006074375A2
公开(公告)日：2006-07-13
申请号：PCT/US2006000470
申请日：2006-01-05
申请人： FRAMATOME ANP INC , CRAWFORD MICHAEL LONG
发明人： CRAWFORD MICHAEL LONG
IPC分类号： G21C19/00
CPC分类号： G21C21/04 , G21C17/06 , G21C21/02
摘要： A method to insert nuclear fuel pellets into a fuel rod cladding tube, having the steps of providing a cladding tube, providing at least one nuclear fuel pellet to be incorporated into the cladding tube, measuring a length of the at least one nuclear fuel pellet with a camera, comparing the length of the at least one nuclear fuel pellet to an expected length, and incorporating the at least one nuclear fuel pellet into the cladding tube when the compared length of the at least one nuclear fuel pellet is within a threshold value of the expected length.
摘要翻译：一种将核燃料颗粒插入燃料棒包壳管中的方法，具有提供包层管的步骤，提供至少一个要包括在包壳管中的核燃料颗粒，测量至少一个核燃料颗粒的长度，相机，将所述至少一个核燃料颗粒的长度与预期长度进行比较，并且当所述至少一个核燃料颗粒的比较长度在所述至少一个核燃料颗粒的阈值内时，将所述至少一个核燃料颗粒结合到所述包壳管中预期长度。

14. 发明申请

WO2004053889A2 BOILING WATER REACTOR NUCLEAR FUEL ASSEMBLY LIFTING SUPPORT 审中-公开
标题翻译：沸腾水反应堆核燃料组件提升支持
公开(公告)号：WO2004053889A2
公开(公告)日：2004-06-24
申请号：PCT/US2003/038515
申请日：2003-12-05
申请人： FRAMATOME ANP INC. , SMITH, Mark, H.
发明人： SMITH, Mark, H.
IPC分类号： G21C
CPC分类号： G21C3/3315 , G21C19/105 , G21Y2002/203 , G21Y2002/304 , G21Y2002/305 , G21Y2004/30 , G21Y2004/501 , G21Y2004/504 , Y02E30/40 , Y10T74/20468
摘要： A lifting support for a boiling water reactor nuclear fuel assembly comprising a grappling head configured to allow attachment to a lifting device, a body with an upper end and a lower end, the upper end connected to the grappling head, the body configured to be inserted into a water channel of a boiling water reactor nuclear fuel assembly, and an end connected to the lower end, the end configured to be accepted by the nuclear fuel assembly.
摘要翻译：一种用于沸水反应堆核燃料组件的提升支撑件，所述提升支撑件包括构造成允许附接至提升装置的抓斗头，具有上端和下端的本体，所述上端连接至抓斗头部，所述主体被构造成插入沸水反应堆核燃料组件的水通道中，并且所述主体的一端连接到所述下端，所述端部被构造成被核燃料组件接受。

15. 发明申请

WO2006135391A3 ELECTROCHEMICAL CORROSION POTENTIAL DEVICE AND METHOD 审中-公开
标题翻译：电化学腐蚀电位器件及方法
公开(公告)号：WO2006135391A3
公开(公告)日：2008-10-30
申请号：PCT/US2005028842
申请日：2005-08-11
申请人： FRAMATOME ANP INC , FRAMATOME ANP GMBH , POP MIHAI G M , LOCKAMON BRIAN G , SELL HANS-JURGEN , KILIAN RENATE
发明人： POP MIHAI G M , LOCKAMON BRIAN G , SELL HANS-JURGEN , KILIAN RENATE
IPC分类号： G21C17/00 , G21C23/00
CPC分类号： G21C17/022 , G01N17/02 , G21Y2002/206 , G21Y2002/304 , G21Y2002/502 , G21Y2004/30 , G21Y2004/40
摘要： The invention provides at least two electrochemical sensors positioned in a nuclear reactor, wherein at least one of the at least two electrochemical sensors has a zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.
摘要翻译：本发明提供了位于核反应堆中的至少两个电化学传感器，其中所述至少两个电化学传感器中的至少一个具有锆电极，并且所述至少两个电化学传感器产生与用于表面的电化学腐蚀电势成比例的电压的至少两个电化学传感器。本发明还提供了一种被配置为接受由至少两个电化学传感器产生的电压的装置，其中所述装置被配置成基于所述至少两个电化学电极的电压来确定所述核反应堆中的锆燃料棒的电化学腐蚀电位传感器。

16. 发明申请

WO2006074375A3 SEGMENT MAKE-UP SYSTEM AND METHOD FOR MANUFACTURING NUCLEAR FUEL RODS 审中-公开
公开(公告)号：WO2006074375A3
公开(公告)日：2006-07-13
申请号：PCT/US2006/000470
申请日：2006-01-05
申请人： FRAMATOME ANP INC. , CRAWFORD, Michael, Long
发明人： CRAWFORD, Michael, Long
IPC分类号： G21C19/00
摘要： A method to insert nuclear fuel pellets into a fuel rod cladding tube, having the steps of providing a cladding tube, providing at least one nuclear fuel pellet to be incorporated into the cladding tube, measuring a length of the at least one nuclear fuel pellet with a camera, comparing the length of the at least one nuclear fuel pellet to an expected length, and incorporating the at least one nuclear fuel pellet into the cladding tube when the compared length of the at least one nuclear fuel pellet is within a threshold value of the expected length.

17. 发明申请

WO2005041208A2 PROCESS FOR MANUFACTURING ENHANCED THERMAL CONDUCTIVITY OXIDE NUCLEAR FUEL AND THE NUCLEAR FUEL 审中-公开
标题翻译：制造增强型导热氧化物核燃料和核燃料的方法
公开(公告)号：WO2005041208A2
公开(公告)日：2005-05-06
申请号：PCT/US2004/034673
申请日：2004-10-21
申请人： FRAMATOME ANP INC. , MCCOY, John, Kevin
发明人： MCCOY, John, Kevin
IPC分类号： G21C
CPC分类号： G21C3/62 , Y02E30/38
摘要： A nuclear fuel and a method to produce a nuclear fuel wherein a porous uranium dioxide arrangement is provided, the arrangement is infiltrated with a precursor liquid and the arrangement is thermally treated such the porous uranium dioxide arrangement is infiltrated with a precursor liquid, followed by a thermal treating of the porous uranium dioxide arrangement with the infiltrated precursor liquid such that the precursor liquid is converted to a second phase.
摘要翻译：核燃料和生产核燃料的方法，其中提供多孔二氧化铀装置，该装置用前体液体渗透，并且该装置被热处理，使得多孔铀二氧化物装置被前体液体渗透，随后是用渗透的前体液体热处理多孔二氧化铀排列，使得前体液体转化为第二相。

18. 发明申请

WO2002003393A3 PRESSURIZED WATER REACTOR FUEL ASSEMBLY SPACER GRID 审中-公开
公开(公告)号：WO2002003393A3
公开(公告)日：2002-01-10
申请号：PCT/US2001/020694
申请日：2001-06-28
申请人： FRAMATOME ANP INC. , VAN SWAM, Leonard, F.P.
发明人： VAN SWAM, Leonard, F.P.
IPC分类号： G21C3/00
摘要： A spacer grid for PWR assemblies (#50) is characterized by curved flow channels (#48) between adjacent fuel rods (#20) and straight, essentially flat strips connecting opposite side plates of the spacer. The latter strips prevent bowing-out of the side plates during fuel assembly fabrication and during operation in the reactor. Additionally, the spacer grid allows accurate positioning of the fuel rods on a square lattice (#50) with a precisely defined pitch, and support of the rods in their spacer cells is such that rod bow will be minimized.

19. 发明申请

WO0203393A2 PRESSURIZED WATER REACTOR FUEL ASSEMBLY SPACER GRID 审中-公开
标题翻译：加压水反应堆燃料组件间隔网
公开(公告)号：WO0203393A2
公开(公告)日：2002-01-10
申请号：PCT/US0120694
申请日：2001-06-28
申请人： FRAMATOME ANP INC , SWAM LEONARD F P VAN
发明人： VAN SWAM LEONARD F P
IPC分类号： G21C3/34 , G21C3/322 , G21C3/352 , G21C3/356 , G21C
CPC分类号： G21C3/352 , G21C3/322 , G21C3/356 , G21C3/3563 , G21Y2002/104 , G21Y2002/204 , G21Y2002/207 , G21Y2004/30 , G21Y2004/302 , Y02E30/32 , Y02E30/38
摘要： A spacer grid for PWR assemblies is characterized by curved flow channels between adjacent fuel rods and straight, essentially flat strips connecting opposite side plates of the spacer. The latter strips prevent bowing-out of the side plates during fuel assembly fabrication and during operation in the reactor. Additionally, the spacer grid allows accurate positioning of the fuel rods on a square lattice with a precisely defined pitch, and support of the rods in their spacer cells is such that rod bow will be minimized. The direction of the nozzles on the flow channels has been chosen to promote cross-flow of the coolant through the assembly.
摘要翻译：用于PWR组件的间隔栅格的特征在于相邻燃料棒之间的弯曲流动通道和连接间隔件的相对侧板的直的基本上平坦的条带。在燃料组装制造期间和在反应器中操作期间，后者的条带防止侧板弯曲。另外，间隔栅格允许将燃料棒精确地定位在具有精确限定的间距的正方形格子上，并且杆在其间隔单元中的支撑使得杆弓将被最小化。已经选择流道上的喷嘴的方向来促进冷却剂通过组件的交叉流动。

20. 发明申请

WO2006007265A2 ULTRASONIC COUNTER-CURRENT SCREW EXTRACTOR FOR URANIUM RECOVERY 审中-公开
标题翻译：用于铀回收的超声波计数电流螺旋萃取器
公开(公告)号：WO2006007265A2
公开(公告)日：2006-01-19
申请号：PCT/US2005/019292
申请日：2005-06-01
申请人： FRAMATOME ANP INC. , KIMURA, Richard, Thaddeus
发明人： KIMURA, Richard, Thaddeus
IPC分类号： C01G56/00
CPC分类号： C01G43/00 , B01D11/0226 , B01D11/0261 , B01D11/0276 , B01D11/0284 , B01F7/00391 , B01F7/021 , C22B3/065 , C22B3/22 , C22B7/007 , C22B7/02 , C22B60/0239 , C22B60/026 , G21F9/30 , Y02P10/234
摘要： An apparatus and method to remove uranium from a body of material wherein the method includes the steps of depositing the body of solid material in an ultrasonic extractor and depositing an amount of acid in the ultrasonic extractor. The method also provides for the steps of heating a jacket of the ultrasonic extractor, transporting the body of solid material in the ultrasonic extractor and the amount of acid such that the body of solid material and the acid contact each other inside the heated ultrasonic extractor while the ultrasonic extractor provides ultrasonic energy to both the body of solid material and the amount of acid, wherein the amount of acid strips uranium from the body of solid material. The method further provides for collecting the amount of acid and the body of solid material in the ultrasonic extractor in different positions, transporting the amount of acid with the stripped uranium to an extraction mixer settler, and settling uranium product from the extraction mixer settler.
摘要翻译：一种从材料体中除去铀的装置和方法，其中所述方法包括以下步骤：将固体物质沉积在超声提取器中并在所述超声提取器中沉积一定量的酸。该方法还提供了加热超声波提取器的护套，在超声波提取器中输送固体材料的体积和酸的量的步骤，使得固体材料和酸的本体在加热的超声波提取器内部彼此接触，同时超声波提取器为固体物质和酸的量提供超声波能量，其中酸性条带从固体材料的主体中排出铀。该方法进一步提供了在不同位置收集超声提取器中的固体物质的酸和体积的量，将带有汽提铀的酸的量输送到萃取混合器沉淀器，以及从萃取混合器沉降器沉淀铀产物。

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