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41. 发明专利

JP2008008744A Gap water quality measuring method and gap water quality measuring instrument 有权
标题翻译： GAP水质测量方法和GAP水质测量仪器
公开(公告)号：JP2008008744A
公开(公告)日：2008-01-17
申请号：JP2006179304
申请日：2006-06-29
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： WADA YOICHI , ISHIDA KAZUNARI , TACHIBANA MASAHIKO , AIZAWA MOTOHIRO , USUI NAOSHI
IPC分类号： G01N27/28 , G01N17/00 , G01N27/07 , G01N27/26 , G01N27/30 , G01N27/416 , G21C17/003 , G21C17/02
摘要： PROBLEM TO BE SOLVED: To provide a gap water quality measuring method for precisely measuring the quantity of state related to the quality of the water in a crack and more precisely estimating a crack developing speed, and a gap water quality measuring instrument. SOLUTION: The gap water quality sensor 36 of the gap water quality measuring instrument 18 has a gap forming member 31 containing gap forming parts 32a and 32b which form a gap 1 and electrodes 2a and 2b are attached to the gap forming part 32b in an electrically insulated state. The electrode 2a is arranged to the opening part 33 of the gap 1 and the electrode 2b is arranged to the leading end part 34 of the gap 1. The measuring instrument 37 of the gap water quality measuring instrument 18 has an ammeter 5 and an electric cable 4 containing wirings 4a and 4b. The wiring 4a is connected to the electrode 2a and the wiring 4b is connected to the electrode 2b. The ammeter 5 measures the current flowing across the electrodes 2a and 2b. COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：提供一种用于精确测量与裂纹中水的质量有关的状态量并更准确地估计裂纹展开速度的间隙水质量测量方法，以及间隙水质量测量仪。间隙水质测量仪18的间隙水质传感器36具有间隙形成部件31，间隙形成部件31包含形成间隙1的间隙形成部32a，32b，电极2a，2b与间隙形成部32b 处于电绝缘状态。电极2a设置在间隙1的开口部33上，电极2b配置在间隙1的前端部34.间隙水质测定器18的测定器37具有电流表5和电电缆4包含布线4a和4b。配线4a与电极2a连接，配线4b与电极2b连接。电流表5测量流过电极2a和2b的电流。版权所有（C）2008，JPO＆INPIT

42. 发明专利

JP2007024644A Adhesion control method of radionuclide on component member of nuclear power plant and film forming method 有权
标题翻译：核电厂组件成员和成膜方法中放射性核素的粘合控制方法
公开(公告)号：JP2007024644A
公开(公告)日：2007-02-01
申请号：JP2005206017
申请日：2005-07-14
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： HOSOKAWA HIDEYUKI , NAGASE MAKOTO , ISHIDA KAZUNARI , WADA YOICHI , USUI NAOSHI , AIZAWA MOTOHIRO , FUSE MOTOMASA
IPC分类号： G21D3/08 , G21C19/307 , G21D1/00
CPC分类号： G21C13/087 , C23F15/00 , G21C19/00 , G21Y2002/201 , G21Y2004/40 , Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide an adhesion control method of radionuclides on a component member of a nuclear power plant.
SOLUTION: During the period from the time of finishing a decontaminating process of removing contaminants formed on the surface of a metallic component member of a nuclear power plant until the time of starting the nuclear power plant, a first chemical containing iron (II) ions, a second chemical for oxidizing the iron (II) ions into iron (III) ions and a third chemical for conditioning the pH of a treatment solution made by mixing the first chemical and the second chemical to 5.5-9.0 are blended in this order, and the resulting mixture is brought into contact with the surface of the metallic member to form a ferrite film. The ferrite film thus formed can inhibit radionuclides from adhering to the surface of the metallic component.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供核电站的部件上的放射性核素的粘附控制方法。解决方案：在完成去除在核电站的金属部件的表面上形成的污染物去除净化处理之前，直到启动核电厂为止，第一种含有铁的化学品（II ）离子，用于将铁（II）离子氧化成铁（III）离子的第二种化学物质和用于调节通过将第一种化学品和第二种化学物质混合制备的处理溶液的pH调节为5.5-9.0的第三种化学品混合在此使所得混合物与金属构件的表面接触以形成铁氧体膜。由此形成的铁氧体膜可以抑制放射性核素附着在金属成分的表面。版权所有（C）2007，JPO＆INPIT

43. 发明专利

JP2005283530A Stress corrosion cracking suppression method 有权
标题翻译：应力腐蚀开裂抑制方法
公开(公告)号：JP2005283530A
公开(公告)日：2005-10-13
申请号：JP2004101804
申请日：2004-03-31
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： WADA YOICHI , ISHIDA KAZUNARI , TACHIBANA MASAHIKO , AIZAWA MOTOHIRO , USUI NAOSHI , NAKAMURA MASAHITO
IPC分类号： G21C19/307 , G21D1/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To suppress stress corrosion cracking by lowering corrosion potential of reactor structure material. SOLUTION: Oxide existing on the surface of structure and piping of a BWR contacting reactor water is removed. Then, hydrazine is added to reactor water together with hydrogen in an operation cycle of a boiling water reactor. As hydrazine is added to the reactor water in addition to hydrogen, oxygen and hydrogen peroxide generated in the reactor are made to react with hydrazine to be water and nitrogen so that the concentration of oxygen and hydrogen peroxide in reactor water is efficiently reduced. Since oxide is removed, the effect of hydrazine to directly lower the corrosion potential of materials can be duplicated. As the results, the corrosion potential of the reactor structure materials sufficiently lowers and stress corrosion cracking can be suppressed. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：通过降低反应堆结构材料的腐蚀电位来抑制应力腐蚀开裂。
解决方案：除去存在于BWR接触反应器水的结构和管道表面上的氧化物。然后，在沸水反应器的操作循环中，将肼与氢气一起加入到反应器水中。当将肼加入反应器中除了氢气之外，使在反应器中产生的氧气和过氧化氢与肼反应成水和氮，从而有效降低反应器水中氧气和过氧化氢的浓度。由于除去氧化物，可以重复肼直接降低材料的腐蚀电位的影响。结果，可以抑制反应堆结构材料的腐蚀电位充分降低，并且可以抑制应力腐蚀开裂。版权所有（C）2006，JPO＆NCIPI

44. 发明专利

JP2005283181A Operation method of residual heat removal system 有权
标题翻译：余热除湿系统的运行方法
公开(公告)号：JP2005283181A
公开(公告)日：2005-10-13
申请号：JP2004094005
申请日：2004-03-29
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： TACHIBANA MASAHIKO , ISHIDA KAZUNARI , WADA YOICHI , USUI NAOSHI
IPC分类号： G21C19/307 , G21D1/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To reduce the quantity of a radioactive nuclide in an oxide film generated on the pipe inner surface in a residual heat removal system.
SOLUTION: A hydrazine injection device is equipped with a hydrazine adjustment tank 23a and a hydrazine injection pipe 20. A hydrazine injection pump 25 and a flow adjustment valve 22a are provided on the hydrazine injection system pipe 20. The hydrazine injection pipe 20 is connected to a residual heat removal system pipe 4 in the residual heat removal system 12. A control rod is inserted into the core to reduce a reactor output, and when the reactor water temperature is lowered to about 150°C, operation of the residual heat removal system 12 is started. A part of reactor water in recirculation system pipe 2 is introduced into the residual heat removal system pipe 4. The flow adjustment valve 22a is opened, and the hydrazine injection pump 25 is driven. Hydrazine in the hydrazine adjustment tank 23a is added to the reactor water flowing in the residual heat removal system pipe 4 through the hydrazine injection pipe 20.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：减少残余散热系统中在管内表面上产生的氧化膜中的放射性核素的量。肼注射装置配备有肼调节罐23a和肼注入管20.肼注射泵25和流量调节阀22a设置在肼注射系统管20上。肼注射管20 连接到残余除热系统12中的残余散热系统管4.控制棒插入到芯中以减少反应器输出，并且当反应器水温降低到约150℃时，残余物的操作散热系统12启动。将再循环系统管2中的反应器水的一部分引入剩余除热系统管4中。打开流量调节阀22a，驱动肼注入泵25。将肼调节槽23a中的肼加入到通过肼注入管20在残余除热系统管4中流动的反应器水中。（C）2006，JPO＆NCIPI

45. 发明专利

JP2007171014A Ecp measurement system in pressurized water reactor, and ecp sensor for therefor 有权
标题翻译：加压水反应器中的ECP测量系统及其ECP传感器
公开(公告)号：JP2007171014A
公开(公告)日：2007-07-05
申请号：JP2005369922
申请日：2005-12-22
申请人： Hitachi Ltd , Japan Atom Power Co Ltd:The , 日本原子力発電株式会社 , 株式会社日立製作所
发明人： TAKIGUCHI HIDEKI , DOZAKI KOJI , NAGATA NOBUAKI , ICHIGE HIDEAKI , USUI NAOSHI , OTA NOBUYUKI
IPC分类号： G21C17/003 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a system which enables ECP measurements in the core of a pressurized water reactor (PWR), without requiring extensive renovation work.
SOLUTION: The ECP measurement system for PWR, which measures ECPs in a core section in the PWR equipped with sheath tubes for inserting thermocouples which are placed so as to reach the core section from outside a reactor vessel and have bending sections and pillars for supporting thermocouple outlet pipes, which include the sheath tubes for inserting the thermocouples upstream from the branching of the sheath tubes for inserting the thermocouples keeps ECP sensors for the PWR inserted thereinto and are mounted on sheath tubes for inserting thermocouples at positions adjacent to the pillars for supporting the thermocouple outlet pipes, after the sheath tubes have come out of them and branched off.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种能够在压水反应堆（PWR）的核心中进行ECP测量的系统，而不需要大量的翻新工作。
解决方案：PWR的ECP测量系统，用于测量PWR的核心部分中的ECP，其中装有用于插入热电偶的护套管，其被放置以从反应堆容器的外部到达核心部分并具有弯曲部分和柱用于支持热电偶出口管，其包括用于将热电偶插入鞘管分支上游的鞘管用于插入热电偶，使得PWR插入其中的ECP传感器被安装在护套管上，用于将热电偶插入与柱子相邻的位置用于支撑热电偶出口管，护套管从其中脱出并分支。版权所有（C）2007，JPO＆INPIT

46. 发明专利

JP2005043051A Method for mitigating stress corrosion cracking in structural material for nuclear power plant 有权
标题翻译：用于减轻核电厂结构材料应力腐蚀开裂的方法
公开(公告)号：JP2005043051A
公开(公告)日：2005-02-17
申请号：JP2003199572
申请日：2003-07-22
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： ISHIDA KAZUNARI , WADA YOICHI , NAGASE MAKOTO , TACHIBANA MASAHIKO , ENDO MASAO , FUSE MOTOMASA , USUI NAOSHI , AIZAWA MOTOHIRO
IPC分类号： G21D3/08 , G21C17/00 , G21D1/00
CPC分类号： G21C17/0225
摘要： PROBLEM TO BE SOLVED: To provide a method for mitigating stress corrosion cracking in a structural material for a nuclear reactor which makes it possible to restrain the dose rate of a main steam pipe from rising without causing such side effects as a rise in the concentration of radioactive cobalt (Co-60) in cooling water for the reactor.
SOLUTION: Reducing nitride containing the nitrogen whose number of oxidations is negative is injected into reactor water in a nuclear power generation plant with a boiling water reactor. The injection of the reducing nitride containing the nitrogen whose number of oxidations is negative into the reactor water makes it possible to mitigate the stress corrosion cracking in the structural material for the reactor without causing such side effects as the rise in the concentration of the cobalt (Co-60).
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：提供一种减轻核反应堆结构材料中的应力腐蚀开裂的方法，其使得可以抑制主蒸汽管的剂量率上升而不会引起副产物的升高反应堆冷却水中放射性钴（Co-60）的浓度。解决方案：将具有氧化数为负的氮的氮化物还原为具有沸水反应器的核发电厂的反应器水中。将含有氧数为负的氮的还原氮氧化物注入反应器水中使得可以减轻反应器的结构材料中的应力腐蚀开裂，而不会引起钴的浓度升高所引起的副作用（钴60）。版权所有（C）2005，JPO＆NCIPI

47. 发明专利

JP2008008750A Corrosive environment determination method of nuclear reactor cooling water, and device therefor 审中-公开
标题翻译：核反应堆冷却水的腐蚀性环境测定方法及其装置
公开(公告)号：JP2008008750A
公开(公告)日：2008-01-17
申请号：JP2006179429
申请日：2006-06-29
申请人： Hitachi Ltd , Tohoku Univ , 国立大学法人東北大学 , 株式会社日立製作所
发明人： UCHIDA SHUNSUKE , SATO YOSHIYUKI , WADA YOICHI , FUSE MOTOMASA , USUI NAOSHI
IPC分类号： G21C17/02 , G01N27/02 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method and a device for selecting a hydrogen peroxide concentration as a corrosive environment index, and determining directly the hydrogen peroxide concentration in high-temperature water.
SOLUTION: A probe supporting a pair of electrodes and a reference electrode by an insulating material is arranged in cooling water in a reactor or in a pipe communicated with the reactor, and either of the pair of electrodes is kept at a natural potential to the reference electrode, and an alternating voltage is applied to the other electrode, and a frequency is changed and a complex impedance between the pair of electrodes is measured. Then, a semicircle diameter on the low frequency side is determined from a Cole-Cole plot of the determined complex impedance, and the hydrogen peroxide concentration in the reactor cooling water is determined from the determined diameter.
COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：提供一种选择过氧化氢浓度作为腐蚀性环境指标的方法和装置，并直接测定高温水中的过氧化氢浓度。解决方案：通过绝缘材料支撑一对电极和参考电极的探针被布置在与反应器连通的反应器或管中的冷却水中，并且一对电极中的任一个保持在自然电位并且向另一个电极施加交流电压，并且改变频率并测量该对电极之间的复阻抗。然后，从确定的复阻抗的Cole-Cole图确定低频侧的半圆直径，根据确定的直径确定反应器冷却水中的过氧化氢浓度。版权所有（C）2008，JPO＆INPIT

48. 发明专利

JP2001083285A BOILING WATER REACTOR PLANT AND ITS OPERATION METHOD 失效
公开(公告)号：JP2001083285A
公开(公告)日：2001-03-30
申请号：JP25839499
申请日：1999-09-13
申请人： HITACHI LTD
发明人： MOCHIZUKI KENTA , ASAKURA YAMATO , USUI NAOSHI
IPC分类号： B01D63/02 , C02F1/42 , C02F1/44 , G21C19/307 , G21D1/00 , G21D1/02 , G21D3/08 , G21F9/06
摘要： PROBLEM TO BE SOLVED: To obtain a reactor plant capable of mitigating Fe concentration lacking in feedwater in plant operation initiation and easy in controlling iron concentration in feedwater. SOLUTION: Feedwater tubing 6 introducing water recovered with a turbine condenser 4 to a reactor 1 as feedwater, a filtering device 8 provided to the feedwater tubing 6 for purifying feedwater, demineralizer 9 placed downstream the filtering device 8 to the feedwater pipe 6 and charged with cation resin of 9% or more degree of crosslinking, and a bypass pipe 10 for bypassing the filtering device, are provided. The cation resin is gel type ion exchanger resin or MR type ion exchanger resin and is desired to have average resin particle size of 900 μm or more.

49. 发明专利

JP2006038623A Nuclear power generation plant with boiling water reactor 有权
标题翻译：具有锅炉水反应堆的核能发电厂
公开(公告)号：JP2006038623A
公开(公告)日：2006-02-09
申请号：JP2004218660
申请日：2004-07-27
申请人： Chubu Electric Power Co Inc , Hitachi Ltd , 中部電力株式会社 , 株式会社日立製作所
发明人： HOSOKAWA HIDEYUKI , USUI NAOSHI , INAGAKI HIROMITSU , OKAMOTO MICHIAKI , OKADA HIDETSUGU
IPC分类号： G21C15/18 , G21C19/307 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power generation plant with a boiling water reactor including a means which can introduce to the residual heat removal systems the water with its quality that can suppress the quantity of generated corrosion products in the storage of carbon steel pipes composing residual heat removal systems during the normal operation of the reactor.
SOLUTION: During the operation of the reactor, pipes in the residual heat removal systems 17 to 25 are stored in a condition where they are filled with suppression pool water. In order to restrain the generation of iron hydroxide from the carbon steel pipes, it is necessary to control the concentration of dissolved oxygen and the conductivity of the stored water. As substitute water systems which can control the conductivity and the concentration of the dissolved oxygen, a device 31 (a nitrogen gas bubbling device) for the deoxidization treatment of the stored water, a device 33 for the desalination treatment of it, a valve 35 for supplying the stored water, and a pump 36, are provided. When the residual heat removal systems are stored with them filled with water during the operation of the reactor, the water in a substitute water storage tank 30 which has undergone at least one of the deoxidization treatment and the desalination treatment is introduced to the residual heat removal systems as the stored water.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：为核能发电厂提供沸水反应堆，其包括能够向剩余散热系统引入的水，其质量可以抑制储存中产生的腐蚀产物的量在反应堆正常运行期间组成残余散热系统的碳钢管。解决方案：在反应器运行期间，剩余散热系统17至25中的管道被储存在充满抑制池水的状态。为了抑制碳钢管中的氢氧化铁的产生，需要控制溶解氧的浓度和储存水的导电性。作为能够控制溶解氧的导电性和浓度的替代水系统，用于对存储水进行脱氧处理的装置31（氮气鼓泡装置），用于其的脱盐处理装置33，用于提供储存的水和泵36。当在反应器运行期间将剩余的除热系统与其充满水一起储存时，已经经历了至少一种脱氧处理和脱盐处理的替代储水箱30中的水被引入到残余热去除系统作为储水。版权所有（C）2006，JPO＆NCIPI

50. 发明专利

JP2006038483A Method of restraining radionuclide from being deposited onto nuclear power plant constitutive member, and film forming device 有权
标题翻译：从放置在核电厂构成部件上的放射性核素的方法和成膜装置
公开(公告)号：JP2006038483A
公开(公告)日：2006-02-09
申请号：JP2004214541
申请日：2004-07-22
申请人： Hitachi Ltd , 株式会社日立製作所
发明人： HOSOKAWA HIDEYUKI , NAGASE MAKOTO , ISHIDA KAZUNARI , WADA YOICHI , USUI NAOSHI , AIZAWA MOTOHIRO , FUSE MOTOMASA
IPC分类号： G21D1/00 , G21F9/00 , G21F9/06 , G21F9/12 , G21F9/28
CPC分类号： G21C19/42 , G21C17/0225 , G21F9/06 , G21F9/12 , G21F9/28
摘要： PROBLEM TO BE SOLVED: To effectively restrain a radionuclide from being deposited onto a nuclear power plant constitutive member. SOLUTION: The first chemical containing ferrous (II) ion, the second chemical for oxidizing the ferrous (II) ion to ferric (III) ion, and the third chemical for regulating a pH of a treating liquid mixed with the first and second chemicals to 5.5-9.0 are brought into contact with a surface of a metal member to form a ferrite coating film, during a period from a finishing stage of a decontaminating process for removing a contaminant formed on the surface of the metal member constituting the nuclear power plant up to time before a start-up of nuclear power plant, and the radionuclide is thereby restrained by the ferrite coating film from being deposited onto the surface of the metal member. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：有效地抑制放射性核素沉积在核电站构成部件上。解决方案：含有亚铁（II）离子的第一种化学物质是将亚铁（II）离子氧化成三价铁离子的第二种化学物质，以及用于调节与第一种和第在除去形成在构成核的金属构件的表面上的污染物的净化处理的整理阶段期间，将第二化学物质5.5-9.0与金属构件的表面接触以形成铁氧体涂膜发电厂在核电厂启动之前，由此被铁氧体涂膜抑制放射性核素沉积在金属部件的表面上。版权所有（C）2006，JPO＆NCIPI

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