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1. 发明专利

JP2012066277A Heat treatment method for branch pipe welded portion, and branch pipe seat structure 审中-公开
标题翻译：分支管焊接部分的热处理方法和分支管座结构
公开(公告)号：JP2012066277A
公开(公告)日：2012-04-05
申请号：JP2010213006
申请日：2010-09-24
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： TSURUKI MASAKI , AOIKE SATOSHI , ORITANI NAOHIKO , FUKUDA YUKA
IPC分类号： B23K31/00 , C21D1/30 , C21D9/08 , C21D9/50
CPC分类号： B23K31/02 , C21D1/30 , C21D9/08 , C21D9/50
摘要： PROBLEM TO BE SOLVED: To provide a heat treatment method which enables an alleviation of tensile residual stress caused by welding or processing of a pipe.SOLUTION: In a heat treatment method in which a small bore pipe having a diameter of not larger than 200 mm and a thickness of not larger than 15 mm is welded to a large bore pipe using a joining joint, heating is made near a welding portion after welding the small bore pipe to the joining joint, and then pipe inner surfaces are cooled with a refrigerant, the distance between a heating area and the large bore pipe is not smaller than 70 mm.
摘要翻译：要解决的问题：提供一种能够减轻焊接或加工管道引起的拉伸残余应力的热处理方法。解决方案：在使用直径不大于200mm，厚度不大于15mm的小孔管焊接到使用接合接头的大孔管的热处理方法中，将小孔管焊接到接合接头后，然后将管内表面用制冷剂冷却的焊接部分，加热区域与大孔管之间的距离不小于70mm。版权所有（C）2012，JPO＆INPIT

2. 发明专利

JP2011225945A Method of and device for heat treatment of stainless steel pipe 审中-公开
标题翻译：不锈钢管热处理方法及装置
公开(公告)号：JP2011225945A
公开(公告)日：2011-11-10
申请号：JP2010097608
申请日：2010-04-21
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： FUKUDA YUKA , ORITANI NAOHIKO , AOIKE SATOSHI
IPC分类号： C21D9/08 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method of and a device for heat treatment of a stainless steel pipe, including: measuring in advance the amount of coolant just after starting of supply to the inside of a pipe residual stress relief unit in an aerial state and controlling the supply of the coolant.SOLUTION: A circulation loop of coolant is formed by a water storage tank, a water feed pump, a flowmeter, pipes, and a channel switching device. The amount of circulating coolant is measured beforehand by the flowmeter in the circulation loop, and controlled to a predetermined amount or more. A channel switching device performs switching so that the supply amount of coolant just after starting of the supply to the residual stress relief unit of the stainless steel pipe whose inside is in an areal state is controlled so as to attain relief of residual stress of the stainless steel pipe by the reliable heat treatment.
摘要翻译：要解决的问题：提供一种不锈钢管的热处理方法和装置，其特征在于，包括：在开始供给到管道残余应力释放单元的内部之后，预先测量冷却剂的量空中状态并控制冷却剂的供应。
解决方案：冷却液的循环回路由储水箱，给水泵，流量计，管道和通道切换装置构成。循环冷却液的量由循环回路中的流量计预先测量，并被控制到一定量以上。通道切换装置执行切换，使得刚刚开始供给到内部处于面状态的不锈钢管的残余应力释放单元之后的冷却剂的供给量被控制，以便消除不锈钢的残余应力钢管通过可靠的热处理。版权所有（C）2012，JPO＆INPIT

3. 发明专利

JP2011105980A Electrolytic etching method and device for surface of structure in nuclear reactor 有权
标题翻译：电解蚀刻方法和核反应堆结构表面装置
公开(公告)号：JP2011105980A
公开(公告)日：2011-06-02
申请号：JP2009260562
申请日：2009-11-16
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： AOIKE SATOSHI , TANAKA MASAAKI , KUROSAWA KOICHI , OKIDO SHINOBU , OMORI SHINYA
IPC分类号： C25F7/00 , C25F3/02 , G01N33/20 , G21C17/003 , G21D1/00
CPC分类号： C25F1/02 , C25F7/00 , G21C17/01 , G21C19/00
摘要： PROBLEM TO BE SOLVED: To provide an electrolytic etching method and a device therefor in which electrolytic etching can be easily performed without largely releasing an etching liquid even in a complicated curved shape in the weld zone at the bottom part of a nuclear reactor, and crystal grain boundaries in the surface of the structure in a nuclear reactor are made visible. SOLUTION: When the surface 13 of the structure in a nuclear rector is subjected to electrolytic etching, a sponge in which a hole is made into a connection structure and an etching liquid are integrated, gelled and arranged in front of an electrode 1,5, the electrode 1,5 is electrically connected with the cathode 11 of a d.c. power source 9, and, in a state of being brought into contact with or made close to the surface 13 of the structure in the furnace electrically connected with the anode 12 of a d.c. power source 9, voltage is applied, and energization is performed. COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：为了提供一种电解蚀刻方法及其装置，其中即使在核反应堆底部的焊接区域中，即使是复杂的弯曲形状，也可以容易地进行电解蚀刻，而不会大幅度地释放蚀刻液体，核反应堆中的结构表面的晶界可见。解决方案：当核反应器中的结构的表面13进行电解蚀刻时，将形成有连接结构的孔和蚀刻液一体化的海绵凝胶化并排列在电极1的前面，5，电极1,5与dc的阴极11电连接电源9，并且处于与直流电极12的电连接的炉中的结构的表面13接触或靠近的状态。电源9，施加电压，并且进行通电。版权所有（C）2011，JPO＆INPIT

4. 发明专利

JP2011080985A Control rod for boiling water reactor 有权
标题翻译：锅炉水反应堆控制系统
公开(公告)号：JP2011080985A
公开(公告)日：2011-04-21
申请号：JP2010202674
申请日：2010-09-10
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： KAWASHIMA NORIO , OIZUMI HIROBUMI , AOIKE SATOSHI
IPC分类号： G21C7/113
CPC分类号： G21C7/113 , Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To provide a control rod for a boiling water reactor, which achieves the improvement in its insertability in case of an earthquake and its life extension as well. SOLUTION: A structural element 103 where a control rod has four blades a', b', c' and d' orthogonal to each other is provided. The four blades have sections 11A, 11B, 11C and 11D filled with neutron absorbers to store them. The structural element 103 has: a first region which has a first cross section forming a first cruciform integral cross section of the four blades coupled to each other in the axial direction of the control rod; a second region which has a second cross section including a separated cross section of each of the four blades; and a third region which has a third cross section including a separated cross section of each of two of the four blades placed orthogonally to the second integral cross section of the two other blades among the four ones coupled by laying them out in the opposite direction and the two other coupled blades. COPYRIGHT: (C)2011,JPO&INPIT
摘要翻译：要解决的问题：提供一种用于沸水反应器的控制棒，其在地震和其寿命延长的情况下实现其可插入性的提高。解决方案：提供了一种结构元件103，其中控制杆具有彼此正交的四个叶片a'，b'，c'和d'。四个叶片具有填充有中子吸收体以存储它们的部分11A，11B，11C和11D。结构元件103具有：第一区域，其具有形成在控制棒的轴向上彼此联接的四个叶片的第一十字形整体横截面的第一横截面; 第二区域，其具有包括四个叶片中的每一个的分离的横截面的第二横截面; 以及第三区域，其具有第三横截面，所述第三横截面包括四个叶片中的两个叶片中的两个的两个的分离横截面，其中四个叶片中的两个与两个其它叶片的第二整体横截面垂直放置，所述四个叶片通过沿相反的方向放置而耦合，另外两个耦合的刀片。版权所有（C）2011，JPO＆INPIT

5. 发明专利

JP2011013128A Metallic structure investigation method and device in reactor 有权
标题翻译：金属结构调查方法和反应器装置
公开(公告)号：JP2011013128A
公开(公告)日：2011-01-20
申请号：JP2009158371
申请日：2009-07-03
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： KUROSAWA KOICHI , OMORI SHINYA , AOIKE SATOSHI , SUGANO AKIHIRO
IPC分类号： G21C17/003
摘要： PROBLEM TO BE SOLVED: To provide a metallic structure investigation method capable of preventing liquid leakage and immersion into an inspection space even to a complicated shape object having a curvature surface in various three-dimensional shapes with CRDs standing in large numbers such as a lower part of a reactor pressure vessel, and on the other hand, when a crack is discovered by any chance on a weld zone of the reactor pressure vessel or a reactor internal structure, it is required to be investigated whether the crack is caused by a stress corrosion crack along a grain boundary structure or not, and therefor, a replica for observing a metallic structure and the state of the cracked surface is required to be collected.SOLUTION: When forming a replica collection space, a filling curing material is injected into the periphery of the space, and a seal tracing the shape of an inspection surface is formed by the filling curing material to thereby acquire a seal shape tracing the shape of the inspection surface.
摘要翻译：要解决的问题：提供一种能够防止液体泄漏并浸入检查空间的金属结构调查方法，即使是具有各种三维形状的曲率表面的复杂形状物体，其中大量数字如下，的反应堆压力容器，另一方面，当在反应堆压力容器的焊接区域或反应堆内部结构上发现任何机会发生裂纹时，需要研究裂纹是否由应力腐蚀引起因此，需要收集用于观察金属结构的复制品和裂纹表面的状态。解决方案：当形成复制收集空间时，将填充固化材料注入外围并且通过填充固化材料形成跟踪检查表面形状的密封件，从而获得跟踪形状的密封形状的检查面。

6. 发明专利

JP2012063182A Crack diagnostic method and crack diagnostic device for reactor structure 有权
标题翻译：用于反应器结构的裂纹诊断方法和裂纹诊断装置
公开(公告)号：JP2012063182A
公开(公告)日：2012-03-29
申请号：JP2010206208
申请日：2010-09-15
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： AOIKE SATOSHI , ITO TAKASHI , TSURUKI MASAKI , WATANABE YOSHIO , MABUCHI YASUHIRO , KUROSAWA KOICHI
IPC分类号： G21C17/00 , G21C17/003
摘要： PROBLEM TO BE SOLVED: To provide a crack diagnostic method of a reactor structure for achieving miniaturization, and for accurately diagnosing the existence of a crack even when an inspection object site exists at a narrow part.SOLUTION: An excitation device 16 is mounted on reactor core spray piping 4 installed in a nuclear reactor pressure container 1, and welded in a nuclear reactor nozzle by using a fixing arm 18 and a movable arm 20. A weight 24 is mounted on a rotary shaft 26 at a position which is different from the position of the center of gravity of the weight 24. The reactor core spray piping 4 is excited due to repeated loads by driving the motor 25 to rotate the weight 24. An accelerator meter 29 measures the characteristic frequency of the excited reactor core spray piping 4, and the characteristic frequency is input to a signal processor 35. The signal processor 35 compares the measured characteristic frequency with the characteristic frequency of the reactor core spray piping 4 in a state that any crack does not exist at the inspection object site, and diagnoses the presence/absence of the crack at the inspection object site.
摘要翻译：要解决的问题：为了提供用于实现小型化的反应器结构的裂纹诊断方法，并且即使当检查对象部位存在于狭窄部分时也能够精确地诊断裂缝的存在。解决方案：激励装置16安装在安装在核反应堆压力容器1中的反应堆芯喷射管道4上，并通过使用固定臂18和可动臂20将其焊接在核反应堆喷嘴中。重物24安装在与重量24的重心位置不同的位置处的旋转轴26上。由于通过驱动马达25以使重物24旋转而反复进行负载，反应堆堆芯喷射管道4被激发。加速器计 29测量被激发的反应堆堆芯喷射管道4的特征频率，并且将特征频率输入到信号处理器35.信号处理器35将测得的特征频率与反应堆堆芯喷射管道4的特征频率进行比较，处于在检查对象部位不存在任何裂纹，并在检查对象部位诊断是否存在裂缝。版权所有（C）2012，JPO＆INPIT

7. 发明专利

JP2011219815A Heat-treatment method for piping 有权
标题翻译：用于管道的热处理方法
公开(公告)号：JP2011219815A
公开(公告)日：2011-11-04
申请号：JP2010089970
申请日：2010-04-09
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： OKIDO SHINOBU , ORITANI NAOHIKO , FUKUDA YUKA , AOIKE SATOSHI , TSURUKI MASAKI
IPC分类号： C21D9/08 , C21D1/30 , C21D9/50
摘要： PROBLEM TO BE SOLVED: To provide a heat-treatment method with which a compressed residual stress part can effectively be formed on the inner surface of a piping in a short time without lowering a strength property of the material.SOLUTION: The heat-treatment method for piping which cools the inner surface of the piping with refrigerant after heating the targeted part for heat-treatment of the piping is provided with a step 24 for heating the targeted part for heat-treatment so as to attain the aimed temperature by using a heating device; a step 45 for cooling the inner surface of the piping by flowing the refrigerant into the inner part of the piping after the target part for heat-treatment attains the aimed temperature; a step 26 for determingng the cooling speed on the outer surface of the piping from the temperature variation on the outer surface of the piping when the inner surface of the piping is cooled; and a step 27 for controlling so that the cooling speed may become equal to or higher than the prescribed speed which is predetermined by repeating the heating step 24 and the cooling step 25 while changing at least either one of the aimed temperature or the flowing rate of the refrigerant when the cooling speed is lower than the prescribed cooling speed which is predetermined.
摘要翻译：要解决的问题：提供一种能够在短时间内有效地在管道内表面上形成压缩残余应力部分而不降低材料的强度特性的热处理方法。解决方案：在加热用于管道热处理的目标部件之后，用制冷剂冷却管道内表面的管道的热处理方法设置有用于加热目标部件进行热处理的步骤24 通过使用加热装置达到目标温度; 步骤45，用于在热处理对象部分达到目标温度之后，通过使制冷剂流入管道的内部来冷却管道的内表面; 当管道的内表面被冷却时，用于从管道外表面的温度变化确定管道外表面上的冷却速度的步骤26; 以及用于进行控制的步骤27，使得冷却速度可以变为等于或高于通过重复加热步骤24和冷却步骤25预定的规定速度，同时改变目标温度或流速当冷却速度低于预定的规定冷却速度时的制冷剂。版权所有（C）2012，JPO＆INPIT

8. 发明专利

JP2015049111A 電磁波放射線の遮蔽体および電磁波放射線の遮蔽方法审中-公开
标题翻译：电磁辐射束的屏蔽体和屏蔽方法
公开(公告)号：JP2015049111A
公开(公告)日：2015-03-16
申请号：JP2013180343
申请日：2013-08-30
申请人：日立Geニュークリア・エナジー株式会社 , Hitachi-Ge Nuclear Energy Ltd
发明人： AOIKE SATOSHI , TACHIBANA MASAHIKO , SHIGENAKA NAOTO , KUROSAWA KOICHI
IPC分类号： G21F1/06 , G01T1/02 , G01T1/16 , G01T1/24 , G21H1/06
摘要：【課題】電磁波放射線に対する遮蔽能力を向上させた、単位厚さ当たりの遮蔽能力が高い電磁波放射線の遮蔽体および電磁波放射線の遮蔽方法を提供する。【解決手段】放射線源1から照射された電磁波放射線2は、遮蔽体3でエネルギーの一部が消費され、遮蔽体3を透過後の電磁波放射線7は透過前の電磁波放射線2に対してエネルギーが減衰される。または、放射線源1から照射された電磁波放射線2は、遮蔽材14の接続部14cにおいてエネルギーの一部を電気エネルギーに変換されて電気消費部16において消費されるため、遮蔽体13を透過後の電磁波放射線17が減衰される。【選択図】図1
摘要翻译：要解决的问题：提供一种电磁辐射束的屏蔽体和屏蔽方法，其提高对电磁辐射束的屏蔽能力，并且具有每单位厚度的高屏蔽能力。解决方案：从一个辐射束辐射的电磁辐射束2的能量的一部分辐射源1被屏蔽体3消耗。穿透屏蔽体3之后的电磁辐射束7的能量在穿透之前被抵抗电磁辐射束2衰减。或者，由于从辐射源1辐射的电磁辐射束2的能量的一部分被转换成屏蔽构件14的连接14c中的电能，以在电力消耗部分16中消耗，电磁辐射束17在穿透屏蔽身体13被衰减。

9. 发明专利

JP2012233749A Nuclear facility, and waste water treating apparatus and waste water treating method thereof 审中-公开
标题翻译：核设施，废水处理装置及废水处理方法
公开(公告)号：JP2012233749A
公开(公告)日：2012-11-29
申请号：JP2011101408
申请日：2011-04-28
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： IIZUKA HIDEHIRO , KAMOSHITA MAMORU , SASAHIRA AKIRA , NOSHITA KENJI , KUMAGAI NAOKI , HINO YUKO , WATANABE DAISUKE , NAGAYAMA TADASHI , AOIKE SATOSHI
IPC分类号： G21F9/12
摘要： PROBLEM TO BE SOLVED: To provide a nuclear facility, and a waste water treating apparatus and waste water treating method thereof, which can remove radioactive nuclide and/or an oil content in waste water from a nuclear reactor building to avoid dispersion of the contaminants to a peripheral environment.SOLUTION: A waste water treating apparatus 100 for purifying waste water from a nuclear facility includes: an oil content removing device 103 for removing an oil content in waste water from a nuclear reactor building 102; and a radioactive nuclide removing device 104 for removing radioactive nuclide in the waste water from the nuclear reactor building 102.
摘要翻译：要解决的问题：提供可以从核反应堆建筑物中去除放射性核素和/或废水中的油含量的废水处理设备和废水处理设备及其废水处理方法，以避免分散污染物到外围环境。解决方案：用于从核设施净化废水的废水处理装置100包括：用于从核反应堆建筑物102除去废水中的油含量的含油去除装置103; 以及用于从核反应堆建筑物102去除废水中的放射性核素的放射性核素去除装置104.版权所有（C）2013，JPO＆INPIT

10. 发明专利

JP2012225671A Remote surface survey device, remote surface survey method, and underwater remote surface survey method for structure in nuclear reactor 有权
标题翻译：远程表面测量装置，远程表面测量方法和核反应堆结构的水下远程表面测量方法
公开(公告)号：JP2012225671A
公开(公告)日：2012-11-15
申请号：JP2011091029
申请日：2011-04-15
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： AOIKE SATOSHI , KUROSAWA KOICHI , OMORI SHINYA
IPC分类号： G01N1/28 , G21C17/00 , G21C17/003 , G21C17/08 , G21C19/02
摘要： PROBLEM TO BE SOLVED: To provide a remote surface survey device capable of easily transferring the surface shape of a structure having a complicated curved surface at a location difficult for a person to directly access to a replica for observing the surface shape, without formation of a sealed space; a remote surface survey method; or an underwater remote surface survey method for a structure in a nuclear reactor.SOLUTION: In sampling the replica of the surface shape of a structure, a gap is formed along a specimen surface, so that a replica agent is supplied in the gap. The formation of the gap allows the replica agent to be retained in the gap due to the surface tension of the replica agent. Consequently, the replica of the surface shape of the specimen can be sampled without formation of a sealed space.
摘要翻译：要解决的问题：为了提供一种远程表面测量装置，能够容易地将具有复杂曲面的结构的表面形状转移到难以人直接访问副本以便观察表面形状的位置，而不需要形成密封空间; 远程测量方法; 或用于核反应堆中的结构的水下远程表面测量方法。解决方案：在对结构的表面形状的复制品进行取样时，沿着试样表面形成间隙，从而在间隙中提供复制剂。间隙的形成允许复制剂由于复制剂的表面张力而保留在间隙中。因此，样本的表面形状的复制品可以被采样而不形成密封空间。版权所有（C）2013，JPO＆INPIT

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