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1. 发明申请

WO2006135391A2 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：WO2006135391A2
公开(公告)日：2006-12-21
申请号：PCT/US2005/028842
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
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。

2. 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。

3. 发明申请

WO1997035366A1 CONNECTOR 审中-公开
标题翻译：连接器
公开(公告)号：WO1997035366A1
公开(公告)日：1997-09-25
申请号：PCT/JP1997000900
申请日：1997-03-19
申请人： FRAMATOME CONNECTORS JAPAN LTD. , FRAMATOME CONNECTORS INTERNATIONAL , KOGA, Masahiro , KODAIRA, Yoshihiko
发明人： FRAMATOME CONNECTORS JAPAN LTD. , FRAMATOME CONNECTORS INTERNATIONAL
IPC分类号： H01R23/68
CPC分类号： H01R12/716 , H01R12/57
摘要： A connector (21) is made up of a receptacle housing (26) fixed to one wiring board (22), and a plug housing (27) fixed to another wiring board (24). At least one of an inner surface of a side wall (26a) of the receptacle housing (26) and a side surface (27a) of the plug housing (27) is provided with a projection (26c) which projects towards the plug housing (27) from the vicinity of the bottom surface (26b) of the receptacle housing (26) when the two housings (26, 27) are fitted to each other. The size C1 of the fit clearance between the two housings (26, 27) at the projection (26c) is smaller than C2 of the fit clearance between the housings (26, 27) at the area other than the projection (26c).
摘要翻译：连接器（21）由固定到一个布线板（22）的插座壳体（26）和固定到另一布线板（24）的插头壳体（27）组成。插座壳体（26）的侧壁（26a）的内表面和插头壳体（27）的侧表面（27a）中的至少一个设置有向插头壳体突出的突起（26c）当两个壳体（26,27）彼此嵌合时，从插座壳体（26）的底表面（26b）附近。突出部26c处的两个壳体26,27之间的配合间隙的尺寸C1小于突出部26c以外的区域的壳体26,27之间的配合间隙的C2。

4. 发明申请

WO2023072937A1 COMPUTER IMPLEMENTED METHOD FOR SIMULATING AN OPERATION OF A REACTOR CORE 审中-公开
公开(公告)号：WO2023072937A1
公开(公告)日：2023-05-04
申请号：PCT/EP2022/079792
申请日：2022-10-25
申请人： FRAMATOME
发明人： VAN GEEMERT, René
IPC分类号： G21D3/00 , G21C17/00
摘要： The present invention concerns a computer implemented method for simulating an operation of a reactor core (7), the method comprising: determining (100) an initial state of the reactor core (7), the reactor core (7) comprising a plurality of fuel assemblies (10), wherein the core is partitioned in cubes to constitute nodes of a grid; calculating (102, 104), based on the initial state, a nodal target power distribution (p) and/or the target 3D neutron flux distribution (Φ); obtaining (106) an actual power distribution and/or the actual 3D neutron flux distribution of the nuclear reactor core; determining (108) a difference between the target power distribution (p) and the actual power distribution of the nuclear reactor core and/or determining (108) a difference (δΦ) between the target 3D neutron flux distribution (Φ) and the actual 3D neutron flux distribution of the nuclear reactor core; determining (110) modal expansion coeﬃcients (δcℓ) using a Fourier modal decomposition based on the determined difference (δΦ) and applying a Modal Generalized Perturbation Theory, MGPT, to the modal expansion coefficients (δcℓ) for determining a 3D cross-section distribution perturbation (δΣ) causing the determined difference (δΦ); and determining (112) a 3D adaptation distribution (δx) for the determined difference (δΦ) based on the determined 3D cross-section distribution perturbation (δΣ).

5. 发明申请

WO2023036792A1 PROCÉDÉ ET SYSTÈME DE SURVEILLANCE D'UNE CENTRALE NUCLÉAIRE AVEC DÉTECTION ET CARACTÉRISATION D'UN DÉSÉQUILIBRE 审中-公开
公开(公告)号：WO2023036792A1
公开(公告)日：2023-03-16
申请号：PCT/EP2022/074781
申请日：2022-09-07
申请人： FRAMATOME
发明人： FEINGOLD, Jean
IPC分类号： F22B35/00 , F22B35/18 , G21D3/00 , G21D3/08 , G21D3/04
摘要： Le procédé de surveillance comprend, pour chaque générateur de vapeur parmi plusieurs générateurs de vapeur et pour au moins un des paramètres d'un jeu de paramètres représentatifs du fonctionnement du générateur de vapeur : - la détermination d'un écart entre une valeur mesurée du paramètre pour ce générateur de vapeur et la valeur moyenne de ce paramètre pour l'ensemble des générateurs de vapeur pour détecter un déséquilibre de ce paramètre sur le générateur de vapeur; et - la caractérisation du déséquilibre en fonction d'un ou plusieurs autre(s) paramètre(s) du jeu de paramètres représentatifs, de manière à générer un signal de problème physique ou un signal de dérive de mesure.

6. 发明申请

WO2022129567A1 CONNECTION ARRANGEMENT FOR MECHANICALLY CONNECTING A FIRST ELEMENT AND A SECOND ELEMENT, SUCH AS A GUIDE TUBE AND A TIE PLATE OF A NUCLEAR FUEL ASSEMBLY 审中-公开
公开(公告)号：WO2022129567A1
公开(公告)日：2022-06-23
申请号：PCT/EP2021/086586
申请日：2021-12-17
申请人： FRAMATOME
发明人： LABARRIERE, Eric
IPC分类号： G21C3/334 , F16B7/20
摘要： Connection arrangement for mechanically connecting a first element and a second element, such as a guide tube and a tie plate of a nuclear fuel assembly The connection arrangement is for the mechanical connection of a first element (4) having a connection portion (8) to a second element (6) having a housing (10), the connection arrangement comprising a connection ring (12) received inside the housing (10) with being pivotable between an insertion/extraction position allowing insertion/extraction of the connection portion (8) into the housing (10) and a connection position preventing extraction of the connection portion (8) from the housing (10), and a locking ring (20) axially movable along the center axis (A) between a locked position preventing rotation of the connection ring (12) and an unlocked position allowing rotation of the connection ring (12) between the connection position and the insertion/extraction position.

7. 发明申请

WO2022073896A1 PROCÉDÉ DE FABRICATION D'UN COMPOSANT DE RÉACTEUR NUCLÉAIRE REVÊTU MUNI D'UN MARQUAGE 审中-公开
公开(公告)号：WO2022073896A1
公开(公告)日：2022-04-14
申请号：PCT/EP2021/077226
申请日：2021-10-04
申请人： FRAMATOME
发明人： GOUEREC, Thierry , AUBRY, Axel
IPC分类号： G21C3/06 , G21C17/06 , G21C21/02 , G21C3/04
摘要： Le procédé de fabrication permet d'obtenir un composant de réacteur nucléaire comprenant un substrat (4) et un revêtement (8) recouvrant une surface (4A) du substrat. Le procédé de fabrication comprend le marquage au laser d'un motif (6) sur la surface (4A) du substrat (4), le marquage étant réalisé de manière à former des reliefs en creux (10) dessinant le motif (6) dans la surface (4A) du substrat (4), puis l'application du revêtement (8) sur la surface (4A) du substrat (4), par-dessus le motif (6).

8. 发明申请

WO2021001036A1 HYDROGENATION SYSTEM FOR A PRESSURIZED WATER REACTOR AND ACCORDING METHOD 审中-公开
公开(公告)号：WO2021001036A1
公开(公告)日：2021-01-07
申请号：PCT/EP2019/067839
申请日：2019-07-03
申请人： FRAMATOME GMBH
发明人： BEWER, Marco , NIEDERMEYER, Jörg , BENECKE, Martin
IPC分类号： G21C17/022
摘要： The invention relates to a pressurized water reactor (2), comprising a primary reactor coolant circuit (4) flown through by a primary reactor coolant during operation, and comprising a chemical and volume control system (14) for the primary reactor coolant, the chemical and volume control system (14) comprising, along the direction of flow of the primary reactor coolant, a letdown line (18), a high-pressure charging pump (32) with a given discharge pressure, and a charging line (34) leading to the primary reactor coolant circuit (4), the chemical and volume control system (14) further comprising a hydrogenation system (16) with a hydrogen supply (16) and a hydrogen feeding line (38). In order to achieve efficient and fast hydrogen injection into the primary reactor coolant, a high-pressure feeding pump (40) is arranged in the feeding line (38) to provide a gas pressure higher than the discharge pressure of the charging pump (32), wherein the feeding line (38) discharges into the charging line (34).

9. 发明申请

WO2020249238A1 PROBE SUPPORT APPARATUS FOR AN ULTRASONIC FLAW DETECTOR, ULTRASONIC FLAW DETECTOR AND METHOD FOR INSPECTING A WHEELSET AXLE 审中-公开
公开(公告)号：WO2020249238A1
公开(公告)日：2020-12-17
申请号：PCT/EP2019/065738
申请日：2019-06-14
申请人： FRAMATOME GMBH
发明人： REHFELDT, Thomas , BRESLER, Johannes , FRIEDRICH, Christian
IPC分类号： G01N29/22 , G01M17/08 , G01N29/24 , G01N29/265
摘要： A probe support apparatus (12) for an ultrasonic flaw detector (10) is described. It comprises a probe holder (20) having at least two receptacles (42, 44) for ultrasonic probes (14, 16), and at least two magnetic rollers (22). The receptacles (42, 44) are inclined towards each other such that a middle axis (46) of a first receptacle (42) and a middle axis (48) of a second receptacle (44) are perpendicular to the axes (24) of rotation of the rollers (22). Additionally, an ultrasonic flaw detector (10) comprising such a probe support apparatus (12) is presented. Furthermore, a method for inspecting a wheelset axle using an ultrasonic flaw detector (10) is provided.

10. 发明申请

WO2020244762A1 DEGASIFICATION SYSTEM FOR A NUCLEAR POWER PLANT AND METHOD FOR DEGASSING A FLOW OF REACTOR COOLANT 审中-公开
公开(公告)号：WO2020244762A1
公开(公告)日：2020-12-10
申请号：PCT/EP2019/064827
申请日：2019-06-06
申请人： FRAMATOME GMBH
发明人： NIEDERMEYER, Jörg , BEWER, Marco
IPC分类号： G21C19/307 , B01D19/00
摘要： The invention relates to a nuclear power plant comprising a nuclear reactor and a reactor coolant circuit containing a reactor coolant, and further comprising a degasification system (2) for the reactor coolant. An objective underlying the pre- sent invention is to provide a nuclear power plant with a degasification system (2) which can be easily integrated into the surrounding systems with low space- demand, which in the case of existing plants can be adapted to various needs, and which works reliably and efficiently. To this end, the degasification system (2) is an ultrasonic degasification system comprising a sonotrode cluster (11) with at least one sonotrode (10) arranged in a line of the reactor coolant circuit or in a line which is fluidically connected to the reactor coolant circuit.

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