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61. 发明公开

EP0724929A2 Underwater laser processing method and apparatus 失效
标题翻译：未成年人behandlungsverfahren und -vorrichtung
公开(公告)号：EP0724929A2
公开(公告)日：1996-08-07
申请号：EP96101295.2
申请日：1996-01-30
申请人： KABUSHIKI KAISHA TOSHIBA
发明人： Okazaki, Kouki , Ito, Arata , Sano, Yuji , Mukai, Naruhiko , Aoki, Nobutada , Konagai, Chikara , Kikunaga, Muneyoshi
IPC分类号： B23K26/12
CPC分类号： B23K26/0608 , B23K26/0069 , B23K26/082 , B23K26/0821 , B23K26/1224 , B23K26/142 , G21C13/087 , G21Y2002/10 , G21Y2004/201 , G21Y2004/504 , Y02E30/40
摘要： An underwater laser processing method is carried out by irradiating, through a laser beam irradiation apparatus, a laser beam having a high output, a short pulse and a visible wavelength to a surface of a structure immersed in a water to improve residual stress of a material of the surface of the structure and remove a crack or a CRUD thereof. The laser beam irradiation apparatus comprises a pulse laser device suspended into a water in which a metal material is accommodated from an upper side thereof for irradiating a laser beam having a visible wavelength to a processing position, a beam strength adjusting device for adjusting an output per 1 pulse of a laser beam generated by the pulse laser device and a mechanism for adjusting a spot diameter and a multiplexing ratio of an irradiated beam.
摘要翻译：通过激光束照射装置将具有高输出，短脉冲和可见波长的激光束照射到浸入水中的结构的表面，从而改善材料的残余应力来进行水中激光加工方法的结构的表面，并去除裂纹或其CRUD。激光束照射装置包括：悬挂在水中的脉冲激光装置，其中从其上侧容纳有金属材料，用于将具有可见波长的激光束照射到处理位置，光束强度调节装置，用于调节每个由脉冲激光装置产生的激光束的1脉冲和用于调整照射光束的光点直径和复用比率的机构。

62. 发明公开

EP0500656A1 FLÜSSIGMETALLGEKÜHLTER KERNREAKTOR 失效
标题翻译：液态金属冷却核反应堆。
公开(公告)号：EP0500656A1
公开(公告)日：1992-09-02
申请号：EP90916698.0
申请日：1990-11-15
申请人： Siemens Aktiengesellschaft
发明人： HAMMERS, Heinz-Wilhelm
IPC分类号： G21C1 , G21C13 , G21C15
CPC分类号： G21C1/03 , G21C13/087 , G21C15/18 , Y02E30/34 , Y02E30/35
摘要： Un réacteur nucléaire refroidi par métal liquide, destiné à une centrale nucléaire modulaire, est logé dans une caverne de réacteur (3) pourvue de surfaces de refroidissement (4). Le réacteur comprend une cuve (1) qui renferme un coeur (12), un ou plusieurs échangeurs de chaleur (18) et des pompes primaires. Elle est entourée d'une double cuve (2) en fonte qui fait office d'accumulateur de chaleur et qui est constituée d'une pluralité d'anneaux superposés (2a) et d'un socle (2b). Cet agencement simplifie la structure et facilite le fonctionnement, le contrôle et la réparation ou le remplacement. La fabrication de la double cuve (2) en fonte offre des avantages appréciables pour la conception de l'installation complète, s'agissant des influences externes. La fonction accumulateur de chaleur offre des avantages appréciables pour la conception des systèmes de dissipation thermique des surfaces de refroidissement (4).

63. 发明公开

EP0403756A1 Reactor vessel annealing system 失效
标题翻译： Einrichtung zumGlüheneinesReaktorbehälters。
公开(公告)号：EP0403756A1
公开(公告)日：1990-12-27
申请号：EP90107324.7
申请日：1990-04-18
申请人： WESTINGHOUSE ELECTRIC CORPORATION
发明人： Miller, Philip Edward , Katz, Leonard R. , Nath, Raymond John , Blaushild, Ronald Maxim , Tatch, Michael D. , Kordalski, Frank Joseph , Wykstra, Donald Thomas , Kavalkovich, William Michael
IPC分类号： G21C13/087
CPC分类号： G21C13/087 , B60P3/14 , Y02E30/40
摘要： A system for annealing a vessel (14) in situ by heating the vessel (14) to a defined temperature, composed of: an electrically operated heater assembly (10) insertable into the vessel (14) for heating the vessel (14) to the defined temperature; temperature monitoring components positioned relative to the heater assembly (10) for monitoring the temperature of the vessel (14); a controllable electric power supply unit for supplying electric power required by the heater assembly (10); a control unit for controlling the power supplied by the power supply unit; a first vehicle (2) containing the power supply unit; a second vehicle (4) containing the control unit; power conductors (22) connectable between the power supply unit and the heater unit (10) for delivering the power supplied by the power supply unit to the heater assembly (10); signal conductors (20,24) connectable between the temperature monitoring components and the control unit for delivering temperature indicating signals from the temperature monitoring components to the control unit; and control conductors (8) connectable between the control unit and the power supply unit for delivering to the power supply unit control signals for controlling the level of power supplied by the power supply unit to the heater assembly (10). At least one of the vehicles is constructed to support comparatively heavy loads while being capable of being loaded and unloaded from essentially any location along either side of the vehicle. At least one vehicle is provided with a capable connecting unit which provides a stress-relief support for at least one set of cables. The system further includes apparatus for maintaining the interior of the vessel at subatmospheric pressure during annealing.
摘要翻译：一种用于通过将容器（14）加热到限定温度来原位退火容器（14）的系统，该系统由以下部件组成：电动加热器组件（10），其可插入容器（14）中，用于将容器（14）加热到定义温度; 相对于加热器组件（10）定位的用于监测容器（14）的温度的温度监控部件; 用于提供加热器组件（10）所需的电力的可控电力供应单元; 控制单元，用于控制由电源单元提供的电力; 包含电源单元的第一车辆（2）; 包含所述控制单元的第二车辆（4）电源导体（22）可连接在电源单元和加热器单元（10）之间，用于将由电源单元提供的电力传送到加热器组件（10）; 信号导体（20,24），其可连接在所述温度监测部件和所述控制单元之间，用于将温度指示信号从所述温度监控部件传送到所述控制单元; 以及可连接在控制单元和电源单元之间的控制导体（8），用于向电源单元输送控制信号，以控制由电源单元提供给加热器组件（10）的电力电平。至少一个车辆被构造成支撑比较重的载荷，同时能够从基本上沿着车辆两侧的任何位置装载和卸载。至少一个车辆设置有能力连接单元，其为至少一组电缆提供应力消除支撑。该系统还包括用于在退火期间将容器的内部维持在低于大气压的装置。

64. 发明申请

US20160351281A1 Neutron Irradiated Material Repair 审中-公开
标题翻译：中子照射材料修复
公开(公告)号：US20160351281A1
公开(公告)日：2016-12-01
申请号：US14721834
申请日：2015-05-26
申请人： AREVA Inc.
发明人： Jeffrey A. Enneking , Brian W. Ring
IPC分类号： G21C21/18 , B23K26/144 , B23K26/36 , B23P6/00 , B23K26/342
CPC分类号： B23K26/144 , B23K26/0884 , B23K26/1224 , B23K26/127 , B23K26/32 , B23K26/34 , B23K26/361 , B23K2101/12 , B23K2103/04 , B23K2103/26 , B23P6/00 , G21C13/087 , G21C19/02 , G21C19/20 , G21C21/00 , Y02E30/40
摘要： The invention is a process of repairing cracked or microstructurally damaged portions of irradiated materials, such as nuclear reactor pressure vessels and shrouds. A damaged portion of the irradiated substrate is first removed, such as by electrical discharge machining (EDM). After removing the damaged portion, the recast layer inherent in the EDM process is then removed. Once the repair area substrate material has been removed to a calculated depth, the created cavity is then filled without releasing transmutated elements within the irradiated material. A chamber may be placed on the irradiated material surrounding the repair area to create an isolated work space.
摘要翻译：本发明是修复受辐射材料（例如核反应堆压力容器和护罩）的裂纹或微结构损坏部分的方法。照射的基板的损坏部分首先被去除，例如通过放电加工（EDM）。在去除损坏的部分之后，然后去除EDM工艺中固有的重铸层。一旦修复区域基底材料已被去除到计算的深度，则所形成的空腔然后被填充而不释放被照射材料内的变形元素。腔室可以被放置在围绕修复区域的辐射材料上以产生隔离的工作空间。

65. 发明申请

US20140153685A1 System and Method for Annealing Nuclear Fission Reactor Materials 有权
标题翻译：退火核裂变反应堆材料的系统和方法
公开(公告)号：US20140153685A1
公开(公告)日：2014-06-05
申请号：US13916671
申请日：2013-06-13
申请人： Searete LLC
发明人： Charles E. Ahlfeld , John Rogers Gilleland , Roderick A. Hyde , David G. McAlees , Jon David McWhirter , Ashok Odedra , Clarence T. Tegreene , Joshua C. Walter , Kevan D. Weaver , Charles Whitmer , Lowell L. Wood, JR. , George B. Zimmerman
IPC分类号： C21D9/00 , G21C7/32 , G21C7/00
CPC分类号： C21D9/00 , G21C1/026 , G21C3/07 , G21C7/00 , G21C7/32 , G21C13/087 , G21C17/0225 , G21C19/00 , Y02E30/34 , Y02E30/39
摘要： Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.
摘要翻译：说明性实施例提供了与退火核裂变反应堆材料相关的系统，方法，装置和应用。

66. 发明申请

US20100065164A1 System and method for annealing nuclear fission reactor materials 有权
公开(公告)号：US20100065164A1
公开(公告)日：2010-03-18
申请号：US12284338
申请日：2008-09-18
申请人： Charles E. Ahlfeld , John Rogers Gilleland , Roderick A. Hyde , David G. McAlees , Jon David McWhirter , Ashok Odedra , Clarence T. Tegreene , Joshua C. Walter , Kevan D. Weaver , Charles Whitmer , Lowell L. Wood, JR. , George B. Zimmerman
发明人： Charles E. Ahlfeld , John Rogers Gilleland , Roderick A. Hyde , David G. McAlees , Jon David McWhirter , Ashok Odedra , Clarence T. Tegreene , Joshua C. Walter , Kevan D. Weaver , Charles Whitmer , Lowell L. Wood, JR. , George B. Zimmerman
IPC分类号： C21D9/00
CPC分类号： C21D9/00 , G21C1/026 , G21C3/07 , G21C7/00 , G21C7/32 , G21C13/087 , G21C17/0225 , G21C19/00 , Y02E30/34 , Y02E30/39
摘要： Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.

67. 发明申请

US20070127619A1 Suppression method of radionuclide deposition on reactor component of nuclear power plant and ferrite film formation apparatus 有权
标题翻译：核电厂反应堆组件和铁素体成膜装置放射性核素沉积的抑制方法
公开(公告)号：US20070127619A1
公开(公告)日：2007-06-07
申请号：US11485984
申请日：2006-07-14
申请人： Hideyuki Hosokawa , Makoto Nagase , Kazushige Ishida , Youichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
发明人： Hideyuki Hosokawa , Makoto Nagase , Kazushige Ishida , Youichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
IPC分类号： G21C3/00
CPC分类号： G21C13/087 , C23F15/00 , G21C19/00 , G21Y2002/201 , G21Y2004/40 , Y02E30/40
摘要： It is an object of the present invention to efficiently suppress radionuclide deposition on a reactor component of nuclear power plant. Radionuclide deposition on the surface of a metallic reactor component of nuclear power plant is suppressed by forming a ferrite film on the component, wherein the film is formed, after decontamination for removing radionuclides contaminants from the component surface is completed and before the plant is started up, by contacting a treatment solution which mixes a first agent containing the iron (II) ions, a second agent for oxidizing the iron (II) ions into the iron (III) ions and a third agent for adjusting pH level of a solution to 5.5 to 9.0 in this order with the reactor component surface.
摘要翻译：本发明的目的是有效地抑制放射性核素沉积在核电站的反应器部件上。核电站金属反应堆部件表面上的放射性核素沉积被抑制，在部件上形成铁氧体膜，其中形成膜，在从组件表面去除放射性核素污染物的净化完成之后并且在工厂启动之前通过使含有铁（II）离子的第一试剂混合的处理溶液与将铁（II）离子氧化成铁（III）离子的第二试剂和用于将溶液的pH水平调节至5.5的第三试剂接触以9.0的顺序与反应器组件表面。

68. 发明申请

US20030215047A1 Shield building 审中-公开
标题翻译：盾建筑
公开(公告)号：US20030215047A1
公开(公告)日：2003-11-20
申请号：US10422779
申请日：2003-04-25
申请人： Ishikawajima-Harima Heavy Industries Co., Ltd.
发明人： Hiroe Kobayashi , Tatsuya Fujiwaka
IPC分类号： G21C009/00
CPC分类号： G21C13/087 , G21C13/00 , Y02E30/40
摘要： A shield building peripherally surrounds a containment vessel 3 and has an outer wall 9 with air inlets 4 adjacent to an upper end of the outer wall, a roof 10 contiguous with the upper end of the outer wall 9 having a central opening 12 and an inner wall 11 extending downward from a lower surface of the roof 10 adjacent to a peripheral edge of the roof and facing via gaps 13 and 14 to inner and outer peripheries of the outer wall 9 and containment vessel 3, respectively. The outer and inner walls 9 and 11 and the roof 10 are integrally provided by a steel structure to attain simplification in structure and reduction in quantity of the shield building.
摘要翻译：屏蔽建筑外围围绕容纳容器3并且具有外壁9，外壁9具有与外壁的上端相邻的空气入口4，与外壁9的上端邻接的屋顶10具有中心开口12和内壁壁11从屋顶10的下表面向下延伸，邻近屋顶的周边边缘并且经由间隙13和14分别面向外壁9和容纳容器3的内周和外周。外壁9和内壁11以及屋顶10由钢结构一体地提供，以实现盾构结构的结构简化和数量减少。

69. 发明授权

US5987088A Precipitation hardening type single crystal austenitic steel, and usage the same 失效
标题翻译：沉淀硬化型单晶奥氏体钢，用法相同
公开(公告)号：US5987088A
公开(公告)日：1999-11-16
申请号：US63427
申请日：1998-04-21
申请人： Yasuhisa Aono , Akira Yoshinari , Yasuo Kondo , Junya Kaneda , Hideyo Kodama , Takahiko Kato , Shigeo Hattori , Masahiko Arai
发明人： Yasuhisa Aono , Akira Yoshinari , Yasuo Kondo , Junya Kaneda , Hideyo Kodama , Takahiko Kato , Shigeo Hattori , Masahiko Arai
IPC分类号： C30B21/02 , C21D6/00 , C21D6/02 , C22C38/00 , C22C38/40 , C22C38/58 , C22C38/60 , C30B29/52 , C30B33/00 , G21C3/07 , G21C5/10 , G21C13/087 , G21C21/00 , G21C1/04
CPC分类号： G21C21/00 , C21D6/004 , C21D6/02 , C22C38/40 , C30B29/52 , C30B33/00 , G21C13/087 , G21C3/07 , G21C5/10 , C21D2201/04 , C21D2211/001 , G21Y2002/101 , G21Y2002/103 , G21Y2004/10 , G21Y2004/201 , G21Y2004/504 , Y02E30/40 , Y10S376/90
摘要： In order to provide an austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance so as to extend the life of a nuclear reactor core structure, which is used under a high radiation dose environment, a method is employed, which comprises the steps of homogeneously dispersing carbides into a parent phase of the austenitic single crystal stainless steel by a two step solution heat treatment, and subsequently effecting an ageing heat treatment after rapid cooling for precipitating fine carbides. Austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance can be provided, and the life of nuclear reactor core structure, which is used under a high radiation dose environment, can be extended.
摘要翻译：为了提供具有优选的耐应力腐蚀开裂性，强度和照射诱导的耐脆性的奥氏体单晶不锈钢，以延长在高辐射剂量环境下使用的核反应堆核心结构的寿命，方法是其包括通过两步固溶热处理将碳化物均匀分散到奥氏体单晶不锈钢的母相中的步骤，随后在快速冷却后进行时效热处理以沉淀细小的碳化物。可以提供具有优异的抗应力腐蚀开裂性，强度和照射诱导的耐脆性的奥氏体单晶不锈钢，并且可以延长在高辐射剂量环境下使用的核反应堆堆芯结构的寿命。

70. 发明授权

US5687204A Method of and apparatus for checking the degradation of a pressure vessel of a nuclear reactor 失效
标题翻译：用于检查核反应堆压力容器退化的方法和装置
公开(公告)号：US5687204A
公开(公告)日：1997-11-11
申请号：US319629
申请日：1994-10-07
申请人： Katsuyuki Ara , Nobuya Nakajima , Noriya Ebine
发明人： Katsuyuki Ara , Nobuya Nakajima , Noriya Ebine
IPC分类号： G21C13/087 , G21C17/003 , G21C17/00
CPC分类号： G21C13/087 , G21C17/003 , G21Y2002/102 , G21Y2002/204 , Y02E30/40
摘要： In a method of and an apparatus for checking the degradation of the pressure vessel of a nuclear reactor with the pressure vessel of the nuclear reactor being directly measured in a non-destructive manner, a magnetic yoke having an exciting coil and a magnetic flux measuring coil is closely placed in contact with the inner wall of the pressure vessel of the nuclear reactor. The hysteresis magnetization characteristics of the closed magnetic path formed by the magnetic yoke and the pressure vessel of the nuclear reactor are measured. The coercive forces are obtained by the hysteresis characteristics. The hardness of the material comprising the pressure vessel of the nuclear reactor at the part of the magnetic path formed in the pressure vessel of the nuclear reactor is obtained from the coercive forces and the degradation of the material comprising the pressure vessel is checked from the hardness.
摘要翻译：在以非破坏性方式直接测量核反应堆的压力容器的核反应堆的压力容器的劣化检测方法和装置中，具有励磁线圈和磁通量测量线圈的磁轭紧密地与核反应堆的压力容器的内壁接触。测量由磁轭和核反应堆的压力容器形成的闭合磁路的磁滞特性。矫顽力通过滞后特性得到。由核反应堆的压力容器中形成的磁路部分的核反应堆的压力容器的材料的硬度是由矫顽力获得的，并且从包含压力容器的材料的劣化可以从硬度。

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