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1. 发明申请

US20110176649A1 Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant 有权
标题翻译：核电厂反应堆部件放射性核素沉积抑制方法
公开(公告)号：US20110176649A1
公开(公告)日：2011-07-21
申请号：US12984326
申请日：2011-01-04
申请人： Hideyuki HOSOKAWA , Makoto Nagase , Kazushige Ishida , Yoichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
发明人： Hideyuki HOSOKAWA , Makoto Nagase , Kazushige Ishida , Yoichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
IPC分类号： G21C9/00
CPC分类号： G21C19/42 , G21C17/0225 , G21F9/06 , G21F9/12 , G21F9/28
摘要： A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.
摘要翻译：一种抑制放射性核素在核电厂部件上沉积的方法包括通过使含有铁（II）离子的第一化学物质，将铁（II）离子氧化成铁（III）离子的第二种化学物质）与第第三种化学品，用于在去除在金属表面形成的污染物的净化步骤的净化步骤的整理阶段中调节含有第一和第二化学品的混合物的处理溶液的pH为5.5至9.0的金属构件表面构成核电站的成员，并且通过铁氧体膜抑制放射性核素在金属构件上的沉积。

2. 发明申请

US20080292042A1 Method of stress corrosion cracking mitigation for nuclear power plant structural materials 有权
标题翻译：核电厂结构材料应力腐蚀开裂缓解方法
公开(公告)号：US20080292042A1
公开(公告)日：2008-11-27
申请号：US12213316
申请日：2008-06-18
申请人： Kazushige Ishida , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
发明人： Kazushige Ishida , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
IPC分类号： G21C15/00
CPC分类号： G21C17/0225
摘要： The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.
摘要翻译：本发明的目的是提供一种减轻反应堆结构材料的应力腐蚀开裂的方法，其可以抑制主蒸汽管线剂量率的上升而没有二次效应，例如放射性钴-60浓度的升高等等在反应堆水中。将氢和含有负氧化数的氮（例如肼）的还原氮化合物注入沸水核电厂的核心水中。通过将含有负氧化数的氮的还原性氮化合物注入芯水中，可以缓解反应器结构材料的应力腐蚀开裂，而不会发生诸如钴-60等的浓度升高的副反应。

3. 发明申请

US20050018805A1 Method of stress corrosion cracking mitigation for nuclear power plant structural materials 审中-公开
标题翻译：核电厂结构材料应力腐蚀开裂缓解方法
公开(公告)号：US20050018805A1
公开(公告)日：2005-01-27
申请号：US10896092
申请日：2004-07-22
申请人： Kazushige Ishida , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
发明人： Kazushige Ishida , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
IPC分类号： G21D3/08 , G21C17/00 , G21D1/00
CPC分类号： G21C17/0225
摘要： The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.
摘要翻译：本发明的目的是提供一种减轻反应堆结构材料的应力腐蚀开裂的方法，其可以抑制主蒸汽管线剂量率的上升而没有二次效应，例如放射性钴-60浓度的升高等等在反应堆水中。将氢和含有负氧化数的氮（例如肼）的还原氮化合物注入沸水核电厂的核心水中。通过将含有负氧化数的氮的还原性氮化合物注入芯水中，可以缓解反应器结构材料的应力腐蚀开裂，而不会发生诸如钴-60等的浓度升高的副反应。

4. 发明授权

US5111043A Apparatus for material surface observation 失效
标题翻译：用于材料表面观察的装置
公开(公告)号：US5111043A
公开(公告)日：1992-05-05
申请号：US639129
申请日：1991-01-09
申请人： Naoto Shigenaka , Tsuneyuki Hashimoto , Motomasa Fuse
发明人： Naoto Shigenaka , Tsuneyuki Hashimoto , Motomasa Fuse
IPC分类号： G01Q30/02 , H01J37/28
CPC分类号： H01J37/28 , H01J2237/244
摘要： An apparatus of material surface observation related to the present invention is a scanning electron microscope which is combined with an accelerator of charged particles. The material surface is activated by irradiation of the charged particles and a surface reaction is induced. Secondary electron in generated by irradiation of the scanning electron beam depending on a shape of the material surface. The secondary electron generated by the irradiation of the scanning electron beam is discriminated from the secondary electrode generated by the irradiation of the charged particles, and only a signal of the secondary electron generated by the irradiation of the scanning electron beam is visualized. Consequently, a reaction process of the material surface which is activated or is reaction-induced by the irradiation of the charged particles can be observed in atomic level with less noise.
摘要翻译：与本发明有关的材料表面观察装置是与带电粒子的加速器结合的扫描型电子显微镜。材料表面通过照射带电粒子而被激活，并引起表面反应。根据材料表面的形状通过扫描电子束的照射而产生的二次电子。通过照射扫描电子束产生的二次电子与通过照射带电粒子产生的二次电极区分开，只有通过扫描电子束的照射产生的二次电子的信号被可视化。因此，能够以较小的噪音以原子级观察被激发的物质表面或被带电粒子的照射反应的反应过程。

5. 发明授权

US08457270B2 Suppression method of radionuclide deposition on reactor component of nuclear power plant 有权
标题翻译：核电厂反应堆组件放射性核素沉积抑制方法
公开(公告)号：US08457270B2
公开(公告)日：2013-06-04
申请号：US12984326
申请日：2011-01-04
申请人： Hideyuki Hosokawa , Makoto Nagase , Kazushige Ishida , Yoichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
发明人： Hideyuki Hosokawa , Makoto Nagase , Kazushige Ishida , Yoichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
IPC分类号： G21C19/42
CPC分类号： G21C19/42 , G21C17/0225 , G21F9/06 , G21F9/12 , G21F9/28
摘要： A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.
摘要翻译：一种抑制放射性核素在核电厂部件上沉积的方法包括通过使包含铁（II）离子的第一化学品，用于氧化铁（II）离子的第二种化学品与铁（III）离子）接触来形成铁氧体膜，以及第三种化学品，用于在去除在金属表面形成的污染物的净化步骤的净化步骤的整理阶段中将含有第一和第二化学品的混合物的处理溶液的pH调节至5.5至9.0的金属构件表面构成核电站的成员，并且通过铁氧体膜抑制放射性核素在金属构件上的沉积。

6. 发明授权

US07869557B2 Method of stress corrosion cracking mitigating for nuclear power plant structural materials 有权
标题翻译：核电厂结构材料应力腐蚀开裂减轻方法
公开(公告)号：US07869557B2
公开(公告)日：2011-01-11
申请号：US12354925
申请日：2009-01-16
申请人： Kazushige Ishida , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
发明人： Kazushige Ishida , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
IPC分类号： G21C9/00
CPC分类号： G21C17/0225
摘要： The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.
摘要翻译：本发明的目的是提供一种减轻反应堆结构材料的应力腐蚀开裂的方法，其可以抑制主蒸汽管线剂量率的上升而没有二次效应，例如放射性钴-60浓度的升高等等在反应堆水中。将氢和含有负氧化数的氮（例如肼）的还原氮化合物注入沸水核电厂的核心水中。通过将含有负氧化数的氮的还原性氮化合物注入芯水中，可以缓解反应器结构材料的应力腐蚀开裂，而不会发生诸如钴-60等的浓度升高的副反应。

7. 发明授权

US07844024B2 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：US07844024B2
公开(公告)日：2010-11-30
申请号：US12364556
申请日：2009-02-03
申请人： Hideyuki Hosokawa , Makoto Nagase , Kazushige Ishida , Yoichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
发明人： Hideyuki Hosokawa , Makoto Nagase , Kazushige Ishida , Yoichi Wada , Naoshi Usui , Motohiro Aizawa , Motomasa Fuse
IPC分类号： G21C9/00
CPC分类号： G21C19/42 , G21C17/0225 , G21F9/06 , G21F9/12 , G21F9/28
摘要： A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.
摘要翻译：一种抑制放射性核素在核电厂部件上沉积的方法包括通过使包含铁（II）离子的第一化学品，用于氧化铁（II）离子的第二种化学品与铁（III）离子）接触来形成铁氧体膜，以及第三种化学品，用于在去除在金属表面形成的污染物的净化步骤的净化步骤的整理阶段中将含有第一和第二化学品的混合物的处理溶液的pH调节至5.5至9.0的金属构件表面构成核电站的成员，并且通过铁氧体膜抑制放射性核素在金属构件上的沉积。

8. 发明申请

US20090225928A1 METHOD OF STRESS CORROSION CRACKING MITIGATING FOR NUCLEAR POWER PLANT STRUCTURAL MATERIALS 有权
标题翻译：应力腐蚀破坏方法对核电厂结构材料的减轻
公开(公告)号：US20090225928A1
公开(公告)日：2009-09-10
申请号：US12354925
申请日：2009-01-16
申请人： Kazushige ISHIDA , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
发明人： Kazushige ISHIDA , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
IPC分类号： G21C15/00
CPC分类号： G21C17/0225
摘要： The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.
摘要翻译：本发明的目的是提供一种减轻反应堆结构材料的应力腐蚀开裂的方法，其可以抑制主蒸汽管线剂量率的上升而没有二次效应，例如放射性钴-60浓度的升高等等在反应堆水中。将氢和含有负氧化数的氮（例如肼）的还原氮化合物注入沸水核电厂的核心水中。通过将含有负氧化数的氮的还原性氮化合物注入芯水中，可以缓解反应器结构材料的应力腐蚀开裂，而不会发生诸如钴-60等的浓度升高的副反应。

9. 发明申请

US20090190712A1 METHOD OF STRESS CORROSION CRACKING MITIGATION FOR NUCLEAR POWER PLANT STRUCTURAL MATERIALS 有权
标题翻译：核电厂结构材料应力腐蚀开裂缓解方法
公开(公告)号：US20090190712A1
公开(公告)日：2009-07-30
申请号：US12363905
申请日：2009-02-02
申请人： Kazushige ISHIDA , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
发明人： Kazushige ISHIDA , Yoichi Wada , Makoto Nagase , Masahiko Tachibana , Masao Endo , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa
IPC分类号： G21C9/00
CPC分类号： G21C17/0225
摘要： The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.
摘要翻译：本发明的目的是提供一种减轻反应堆结构材料的应力腐蚀开裂的方法，其可以抑制主蒸汽管线剂量率的上升而没有二次效应，例如放射性钴-60浓度的升高等等在反应堆水中。将氢和含有负氧化数的氮（例如肼）的还原氮化合物注入沸水核电厂的核心水中。通过将含有负氧化数的氮的还原性氮化合物注入芯水中，可以缓解反应器结构材料的应力腐蚀开裂，而不会发生诸如钴-60等的浓度升高的副反应。

10. 发明授权

US08524056B2 Electrochemical corrosion potential sensor 有权
标题翻译：电化学腐蚀电位传感器
公开(公告)号：US08524056B2
公开(公告)日：2013-09-03
申请号：US12696355
申请日：2010-01-29
申请人： Kazushige Ishida , Yoichi Wada , Masahiko Tachibana , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa , Nobuyuki Ota
发明人： Kazushige Ishida , Yoichi Wada , Masahiko Tachibana , Motomasa Fuse , Naoshi Usui , Motohiro Aizawa , Nobuyuki Ota
IPC分类号： G01N17/00 , G01N27/26 , G21C9/00
CPC分类号： G21C17/022 , G01N17/04
摘要： An electrochemical corrosion potential sensor (ECP sensor) has an electrode cap, an electrode fixing body, a tubular insulator, a tubular metallic housing, and a conductive wire. Both ends of the tubular insulator are connected to the electrode fixing body and the tubular metallic housing respectively. A conductive wire passes through the tubular insulator and the tubular metallic housing, and is connected to an inner surface of the electrode fixing body. The electrode cap 11 disposed to cover an outer surface of the electrode fixing body. The ECP sensor with such a construction can lengthen the lifetime.
摘要翻译：电化学腐蚀电位传感器（ECP传感器）具有电极盖，电极固定体，管状绝缘体，管状金属外壳和导线。管状绝缘体的两端分别与电极固定体和管状金属外壳连接。导线穿过管状绝缘体和管状金属外壳，并连接到电极固定体的内表面。设置为覆盖电极固定体的外表面的电极帽11。具有这种结构的ECP传感器可以延长使用寿命。

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