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41. 发明授权

US10112224B2 Cladding tube for nuclear fuel rod, method and apparatus for manufacturing a cladding 有权
公开(公告)号：US10112224B2
公开(公告)日：2018-10-30
申请号：US14678767
申请日：2015-04-03
申请人： AREVA NP
发明人： Jean-Luc Doudoux , Eric Galban , Yves Charbonnier , Jerome Boussin , Matthieu Ponce , Jan Patrice Simoneau , Joerg Peucker , Holger Schmidt , Klaus L. Nissen
IPC分类号： B21B21/02 , G21C21/02 , B21H8/00 , G21C3/06 , G21C3/08 , B21B15/00 , B21B25/00 , G21C3/07 , B21B21/00
摘要： A cladding tube for nuclear fuel made from metal and including concave dimples on its external surface. A nuclear fuel assembly includes at least a plurality of nuclear fuel rods provided with such cladding tubes. The cladding tube is advantageously manufactured by pilgrim rolling, the dimples being formed during the pilgrim rolling.

42. 发明授权

US09903473B2 Method for carrying out emergent shaft sealing for reactor coolant pump and shaft sealing assembly 有权
公开(公告)号：US09903473B2
公开(公告)日：2018-02-27
申请号：US15102470
申请日：2014-12-10
申请人： AREVA NP
发明人： Romain Thuillier
IPC分类号： F16J9/00 , F16J15/00 , F04D7/08 , F04D29/14 , F16J15/16 , F16J15/34 , F04D29/12 , F04D7/06
CPC分类号： F16J15/008 , F04D7/06 , F04D7/08 , F04D29/126 , F04D29/146 , F05B2240/57 , F16J15/164 , F16J15/3404
摘要： A method for carrying out emergent shaft sealing for a reactor coolant pump and a shaft sealing assembly is provided. The method comprises the steps that a passive stopping sealing member is arranged in a first sealing assembly and forms an opening under the normal operation condition, without affecting the first sealing assembly using a liquid film formed by fluid static pressure to prevent reactor coolant from leaking along a pump shaft; under the station blackout condition, after sensing high-temperature fluid flowing into the first sealing assembly, the passive stopping sealing member is closed and holds the pump shaft of the reactor coolant pump tightly, the gap between the first sealing assembly and the pump shaft of the reactor coolant pump is blocked, and therefore the reactor coolant is prevented from leaking along the pump shaft.

43. 发明授权

US09889467B2 Method for thermochemically treating a part while masking a portion and corresponding mask 有权
公开(公告)号：US09889467B2
公开(公告)日：2018-02-13
申请号：US14438851
申请日：2013-10-31
申请人： AREVA NP , NITRUVID
发明人： Bernard Delmas , Dominique Hertz , Jean-Paul Lebrun , Bernard Lis , Laurent Poirier
IPC分类号： B05D5/00 , C23C8/04 , C23C16/04 , B05C21/00 , B05D1/32 , B05D7/14 , C23C16/22 , C23C16/513
CPC分类号： B05D5/00 , B05C21/005 , B05D1/32 , B05D7/14 , B05D7/146 , C23C8/04 , C23C16/042 , C23C16/22 , C23C16/513
摘要： A method for thermochemically treating a part while masking a portion and corresponding mask are provided. The method includes the steps of providing a mask comprising a body with a seat, at least a deformable sealing washer located in the seat, and a tightening bushing, the body having a cavity, placing a first portion of the part in the cavity, a second portion of the part being located in a passage in the sealing washer, and a third portion of the part being located outside the mask, moving the tightening bushing to its tightened position so that the sealing washer is deformed and applied against the second portion of the part, and applying a thermochemical treatment to the third portion of the part.

44. 发明授权

US09887017B2 Nuclear facility comprising an anchor device 有权
公开(公告)号：US09887017B2
公开(公告)日：2018-02-06
申请号：US14651933
申请日：2013-12-23
申请人： AREVA NP
发明人： Luc Bresous , Serge Roillet
IPC分类号： G21C19/07 , G21C19/19 , F16B5/02 , F16B5/07
CPC分类号： G21C19/07 , F16B5/0291 , F16B5/07 , G21C19/19
摘要： A nuclear facility comprising an anchor device is provided. This anchor device comprises a female part and a male part. The female part includes a groove extending along a longitudinal axis. The groove has a width which decreases longitudinally and a transverse section. The male part includes a slider with a shape mating that of the groove and is able to be longitudinally inserted into the groove. The transverse section of the groove is configured so as to prevent the extraction of the slider out of the groove transversely to the longitudinal axis. The anchor device includes a locking device able to prevent the slider from longitudinally sliding out of the groove.

45. 发明申请

US20170278587A1 ASSEMBLY FOR ACTING ON THE OUTER SURFACE OF A TUBE, AND CORRESPONDING METHOD 审中-公开
公开(公告)号：US20170278587A1
公开(公告)日：2017-09-28
申请号：US15508481
申请日：2015-09-01
申请人： AREVA NP
发明人： Emmanuel FUTIN , Olivier BERNE , Daniel GRYPCZYNSKI
IPC分类号： G21C17/017 , G21C19/20 , F16L55/18
摘要： An assembly for acting on the outer surface of a tube, and corresponding method are provided. The assembly includes a carrier; at least one inspection or maintenance tool; the carrier includes at least one rolling body; an actuator. The carrier further includes a device for connecting the carrier to the tube, arranged so that the tube absorbs at least 50% of the weight of the carrier and the tool.

46. 发明申请

US20160356487A1 ENHANCED DEVICE FOR PIERCING PLUGS IN A STEAM GENERATOR 有权
标题翻译：一种用于在蒸汽发生器中引爆铅笔的增强装置
公开(公告)号：US20160356487A1
公开(公告)日：2016-12-08
申请号：US14563617
申请日：2014-12-08
申请人： AREVA NP
发明人： Eric MANNEVEAU , Jean-Claude SIMONATO
IPC分类号： F22B37/00 , B23P19/02
CPC分类号： F22B37/003 , B23B41/10 , B23P19/025 , F28F11/02
摘要： An enhancing device for piercing plugs in a steam generator is provided. The enhancing device includes a main body, and a bit, borne by the main body and extending along a longitudinal axis. The bit may be driven into rotation around its longitudinal axis, in order to perform an action for piercing a plug. The device includes a hollow tubular element, extending along the longitudinal axis, while surrounding the bit and coaxially with this bit, the tubular element including an outer surface having a screwing thread, intended to be screwed onto the plug prior to the piercing. The tubular element may be driven into rotation around the longitudinal axis, independently of the rotation of the bit.
摘要翻译：提供一种用于在蒸汽发生器中刺穿塞子的增强装置。增强装置包括主体和由主体承载并沿着纵向轴线延伸的钻头。该钻头可以围绕其纵向轴线被驱动旋转，以便执行用于刺穿塞子的动作。该装置包括一个中空管状元件，沿着纵向轴线延伸，同时围绕该钻头并与该钻头同轴，该管状元件包括一个具有螺纹螺纹的外表面，用于在穿孔之前被拧到塞子上。管状元件可以围绕纵向轴线驱动，而与钻头的旋转无关。

47. 发明申请

US20160061646A1 METHOD OF CALIBRATING A LEVEL SENSOR 审中-公开
标题翻译：校准水平传感器的方法
公开(公告)号：US20160061646A1
公开(公告)日：2016-03-03
申请号：US14781550
申请日：2014-04-04
申请人： AREVA NP
发明人： William MESTIVIER , Sylvain SERRANO
IPC分类号： G01F25/00
CPC分类号： G01F25/0061 , G01F23/14 , G01F23/165
摘要： A method of calibrating a level sensor is provided. The level sensor includes a tube, a lower part of which communicates with a liquid volume, an upper part not being filled with the liquid; and a device for measuring a level of the free surface of the liquid along the tube. The method includes placing the upper part of the inner space at a predetermined pressure; computing a theoretical level of the surface of the liquid; acquiring the measured level measured by the measuring device; comparing the theoretical level and the measured level; and repeating the steps for computing a theoretical level, acquiring a measured level and comparing the theoretical and measured levels after placing the upper part of the inner space at least at a second predetermined pressure.
摘要翻译：提供了一种校准液位传感器的方法。液位传感器包括管，其下部与液体体积连通，上部未被液体填充; 以及用于测量沿着管的液体的自由表面的水平的装置。该方法包括将内部空间的上部放置在预定压力下; 计算液体表面的理论水平; 获取由测量装置测量的测量水平; 比较理论水平和测量水平; 并且重复用于计算理论水平的步骤，在将内部空间的上部至少设置在第二预定压力之后获取测量水平并比较理论水平和测量水平。

48. 发明申请

US20160042823A1 METHODS FOR SIMULATING THE FLOW OF A FLUID IN A VESSEL OF A NUCLEAR REACTOR AND FOR CALCULATING THE MECHANICAL DEFORMATION OF ASSEMBLIES OF A NUCLEAR REACTOR CORE, AND ASSOCIATED COMPUTER PROGRAM PRODUCTS 审中-公开
标题翻译：用于模拟核反应堆容器中流体流动和计算核反应堆芯组装机械变形的方法以及相关计算机程序产品
公开(公告)号：US20160042823A1
公开(公告)日：2016-02-11
申请号：US14782770
申请日：2014-04-04
申请人： AREVA NP
发明人： Nicolas Goreaud , Benjamin Chazot , Jérémy Galpin , Hubert Salaün , Elodie Mery De Montigny
IPC分类号： G21D3/00 , G06F17/18
CPC分类号： G21D3/001 , G06F17/18 , G21D3/005 , Y02E30/40
摘要： A method for simulating the flow of a fluid in a vessel of a nuclear reactor is provided. The nuclear reactor includes the vessel and a core inside the vessel, the core including nuclear fuel assemblies, each one extending in an axial direction, including nuclear fuel rods and a grid for maintaining the rods, and being spaced apart from another by a clearance between the grids in a transverse direction.This method for simulating a fluid flow in the vessel of a nuclear reactor includes determining of head loss coefficients in the core, and computing the fluid pressure and speed component(s) in the core using the equation: ∇P=−K×V where P is the component of the fluid pressure, K is a matrix including the determined head loss coefficients, and V is a vector including the fluid speed component(s).A transverse head loss coefficient in the assemblies is determined from a transverse Reynolds number, and an axial head loss coefficient in the clearance is from the dimension of the clearance in the transverse direction.
摘要翻译：提供了一种用于模拟核反应堆的容器中的流体流动的方法。核反应堆包括容器和容器内部的核心，核心包括核燃料组件，每个核燃料组件沿轴向方向延伸，包括核燃料棒和用于保持棒的栅格，并且与另一个间隔开，网格横向。用于模拟核反应堆的容器中的流体流的该方法包括确定核心中的头部损失系数，以及使用以下等式计算核心中的流体压力和速度分量：∇P= -K×V其中 P是流体压力的分量，K是包括确定的头部损失系数的矩阵，V是包括流体速度分量的矢量。组件中的横向头部损失系数由横向雷诺数确定，间隙中的轴向头部损失系数是横向上间隙的尺寸。

49. 发明申请

US20150050141A1 PASSIVE SHUTDOWN SEALING DEVICE FOR A SHAFT SEALING SYSTEM OF A REACTOR COOLANT PUMP SET 审中-公开
标题翻译：用于反应器冷却泵组的轴封密封件的被动关闭密封装置
公开(公告)号：US20150050141A1
公开(公告)日：2015-02-19
申请号：US14370311
申请日：2012-12-26
申请人： AREVA NP
发明人： Eric Savin
IPC分类号： F04D29/12 , F04D7/08 , F16J15/16 , F04D1/00
CPC分类号： F04D29/126 , F04D1/00 , F04D7/08 , F04D29/146 , F16J15/008 , F16J15/164 , F16J15/3404 , G21C15/243 , Y02E30/40
摘要： This invention relates to a passive shutdown sealing device (20, 40) for a reactor coolant pump set comprising a set of bimetallic strips (21, 41) having a first position called the cold position when the temperature of said bimetallic strips is less than said temperature threshold, and a second position called the hot position when the temperature of said bimetallic strips is greater than said temperature threshold; a sealing ring (23) with an active position when said bimetallic strips (21, 41) are in their hot position and with an inactive position when said bimetallic strips are in their cold position; locking/unlocking means (25) adapted to lock said sealing ring (23) in its inactive position when said bimetallic strips (21, 41) are in their cold position and to release said sealing ring (23) when said bimetallic strips (21, 41) are in their hot position; elastic means (24) adapted to constrain said sealing ring (23) in the active position when said locking/unlocking means (25) are unlocked.
摘要翻译：本发明涉及一种用于反应堆冷却剂泵组的被动关闭密封装置（20,40），其包括一组双金属条（21,41），当双金属条的温度小于所述双金属条时，具有称为冷位置的第一位置当所述双金属条的温度大于所述温度阈值时，称为热位置的第二位置; 当所述双金属条（21,41）处于其热位置时处于活动位置的密封环（23），当所述双金属条处于其冷位置时处于非活动位置; 当所述双金属条（21,41）处于其冷的位置时，适于将所述密封环（23）锁定在其不起作用的位置，并且当所述双金属条（21， 41）处于他们的热点; 当所述锁定/解锁装置（25）被解锁时，适于将所述密封环（23）约束在活动位置的弹性装置（24）。

50. 发明申请

US20140254736A1 METHOD FOR PRODUCING, FROM A PREFORM MADE OF AUSTENITIC STAINLESS STEEL WITH A LOW CARBON CONTENT, A WEAR-RESISTANT AND CORROSION-RESISTANT CLADDING FOR A NUCLEAR REACTOR, CORRESPONDING CLADDING AND CORRESPONDING CONTROL CLUSTER 有权
标题翻译：用于生产具有低碳含量的奥氏体不锈钢的预制件的制造方法，用于核反应堆的耐磨性和耐腐蚀性粘合剂，相应的粘合剂和相应的控制聚集体
公开(公告)号：US20140254736A1
公开(公告)日：2014-09-11
申请号：US14348378
申请日：2012-09-28
申请人： AREVA NP
发明人： Dominique Hertz
IPC分类号： C21D1/72 , G21C7/06 , C23C8/22 , C23C8/38 , C23C8/32
CPC分类号： C21D1/72 , C21D6/004 , C21D8/10 , C21D8/105 , C21D9/08 , C21D9/085 , C21D9/14 , C23C8/02 , C23C8/22 , C23C8/32 , C23C8/38 , C23C8/80 , G21C7/06 , G21C7/10 , G21C21/18 , Y02E30/39
摘要： A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method includes steps of providing a tubular blank in austenitic stainless steel whose carbon content is equal to or lower than 0.03% by weight; shaping the blank; finishing the blank to form the cladding; hardening the outer surface of the cladding by diffusing one or more atomic species; the blank, before the providing step or during the shaping or finishing step, being subjected to at least one solution annealing with sub-steps of: heating the blank to a sufficient temperature and for a sufficient time to solubilise any precipitates present; quenching the blank at a rate allowing the austenitic structure to be maintained in a metastable state at ambient temperature and free of precipitates.
摘要翻译：提供了一种用于生产用于核反应堆的耐磨和耐腐蚀的不锈钢部件的方法。该方法包括在碳含量等于或低于0.03重量％的奥氏体不锈钢中提供管状坯料的步骤; 塑造空白整理坯料以形成包层; 通过扩散一种或多种原子物质来硬化包层的外表面; 坯料在提供步骤之前或在整形或精加工步骤期间，进行至少一个以下子步骤的固溶退火：将坯料加热至足够的时间以溶解存在的任何沉淀物; 以允许奥氏体结构在环境温度下保持亚稳态且没有沉淀物的速率淬火坯料。

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