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1. 发明专利

JP2006029940A Hydrogen injection method for boiling water type nuclear power plant 有权
标题翻译：用于水电核燃料发电厂的氢喷射方法
公开(公告)号：JP2006029940A
公开(公告)日：2006-02-02
申请号：JP2004208210
申请日：2004-07-15
申请人： Chubu Electric Power Co Inc , Chugoku Electric Power Co Inc:The , Hitachi Ltd , Hokuriku Electric Power Co Inc:The , Japan Atom Power Co Ltd:The , Tohoku Electric Power Co Inc , Tokyo Electric Power Co Inc:The , Toshiba Corp , 中国電力株式会社 , 中部電力株式会社 , 北陸電力株式会社 , 日本原子力発電株式会社 , 東京電力株式会社 , 東北電力株式会社 , 株式会社日立製作所 , 株式会社東芝
发明人： TAKIGUCHI HIDEKI , SUZUKI SHUNICHI , TAKAMORI KENRO , ABE AYUMI , NAGATA NOBUAKI , DOZAKI KOJI
IPC分类号： G21D3/08 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a hydrogen injection method for a BWR nuclear power plant capable of restraining SCC from being generated.
SOLUTION: In this hydrogen injection method for the boiling water type nuclear power plant capable of restraining the stress corrosion cracking (SCC) of an in-reactor structural member contacting with nuclear reactor water in the boiling water type nuclear power plant, hydrogen is injected into the reactor water when starting the boiling water type nuclear power plant, to lower an oxidant concentration in the reactor water.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供一种能够抑制SCC产生的BWR核电站的氢气注入方法。解决方案：在这种能够抑制沸水型核电厂与核反应堆水接触的反应堆内结构构件的应力腐蚀开裂（SCC）的沸水型核电站的氢气注入方法中，氢气在启动沸水型核电厂时，将其注入反应器水中，以降低反应器水中的氧化剂浓度。版权所有（C）2006，JPO＆NCIPI

2. 发明专利

JP2005003565A Corrosion reduction method for reactor structural material 有权
标题翻译：用于反应器结构材料的腐蚀减少方法
公开(公告)号：JP2005003565A
公开(公告)日：2005-01-06
申请号：JP2003168637
申请日：2003-06-13
申请人： Ishikawajima Harima Heavy Ind Co Ltd , Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝 , 石川島播磨重工業株式会社
发明人： YOTSUYANAGI TADASHI , TAKAGI JUNICHI , YAMAZAKI KENJI , ICHIKAWA NAGAYOSHI , YAMAMOTO SEIJI , OSATO TETSUO , SUZUKI SHUNICHI , TAKAMORI KENRO , SANHONGI MITSURU , FUKAYA YUICHI , HIRANO TAKASHI
IPC分类号： G21C19/307 , G21D1/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To reduce stress corrosion cracking of an reactor structural material within small ranges of water quality variation and dose rate rise in main steam pipes.
SOLUTION: On the surface of reactor structural materials, an exciting current generation material represented by titanium oxide and a noble metal rasing the efficiency of exciting current extraction are deposited. Reactor water to which the material is exposed is set at a condition corresponding to very small hydrogen injection quantity. By this, corrosion potential can be made below a threshold level and stress corrosion cracking of reactor structural material can be suppressed.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：在主要蒸汽管道的水质变化和剂量率上升范围内，减少反应堆结构材料的应力腐蚀开裂。解决方案：在反应堆结构材料的表面上，沉积由氧化钛和贵金属代表的励磁电流产生材料，以提高激发电流提取的效率。将材料暴露于的反应器水设定在与非常小的氢喷射量对应的状态。由此，可以使腐蚀电位低于阈值水平，并且可以抑制反应堆结构材料的应力腐蚀开裂。版权所有（C）2005，JPO＆NCIPI

3. 发明专利

JP2004077320A Method of reducing dose in turbine system 有权
公开(公告)号：JP2004077320A
公开(公告)日：2004-03-11
申请号：JP2002238996
申请日：2002-08-20
申请人： Ishikawajima Harima Heavy Ind Co Ltd , Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝 , 石川島播磨重工業株式会社
发明人： YAMAMOTO SEIJI , OSATO TETSUO , ICHIKAWA NAGAYOSHI , YAMAZAKI KENJI , TAKAGI JUNICHI , YOTSUYANAGI TADASHI , SUZUKI SHUNICHI , TAKAMORI KENRO , SANHONGI MITSURU , FUKAYA YUICHI , HIRANO TAKASHI
IPC分类号： G21D3/08 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To reduce the exposure of workers to radiation by reducing the transiting amount of radioactive nitrogen to a turbine system in a BWR power plant.
SOLUTION: In a boiling water reactor 1, a substance for producing oxidizing radicals, such as titanium oxide, is injected into cooling water from at least one of a nuclear reactor recirculation system line 5, a nuclear reactor cooling material purifying system line 7, a feed water line 8, and a nuclear reactor residual heat removal system line 11. Nitrogen compounds are oxidized by oxidizing radicals, such as OH, produced on surfaces of the injected titanium oxide and turned into a form stable in liquid phase, and the transiting amount of radioactive nitrogen to the turbine system is reduced. This lowers doses in the turbine system, and reduces the exposure of workers to radiation.
COPYRIGHT: (C)2004,JPO

4. 发明专利

JP2006162522A Nuclear power plant, anticorrosion coating film forming method therefor, and nuclear reactor operation method 有权
标题翻译：核电厂，其抗静电涂膜成膜方法及核反应堆运行方法
公开(公告)号：JP2006162522A
公开(公告)日：2006-06-22
申请号：JP2004357319
申请日：2004-12-09
申请人： Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝
发明人： OKAMURA MASAHITO , OSATO TETSUO , YAMAMOTO SEIJI , YOTSUYANAGI TADASHI , ICHIKAWA NAGAYOSHI , YAMAZAKI KENJI , TAKAGI JUNICHI , URATA HIDEHIRO , SUZUKI SHUNICHI , TAKAMORI KENRO , SUZUKI JUNICHI
IPC分类号： G21D1/00 , G21C19/307 , G21D3/08
CPC分类号： G21C17/0225 , G21C13/08 , G21C17/022 , G21Y2002/103 , G21Y2004/10 , Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power plant capable of restraining surely each portion of a nuclear reactor structural material from corroding due to stress corrosion cracking, and capable of effectively maintaining corrosion restraint, and to provide an anticorrosion coating film forming method therefor, and a nuclear reactor operation method. SOLUTION: In this nuclear power plant, the anticorrosive oxide coating film 51 containing an oxide, having a property of a P-type semiconductor, is formed on a metal member 50 surface, such as the nuclear reactor structural material or the like exposed to high temperature water, a catalytic substance 52 having the properties of an N-type semiconductor is deposited on the oxide film 51, and the oxide film 51 is constituted to maintain the properties of the P-type semiconductor. COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供能够确保核反应堆结构材料的每个部分由于应力腐蚀开裂而腐蚀并能够有效地保持腐蚀约束的核电站，并提供防腐涂膜成型方法，以及核反应堆操作方法。解决方案：在该核电站中，在金属构件50表面上形成含有P型半导体的性质的氧化物的防腐氧化物涂膜51，例如核反应堆结构材料等暴露于高温水中，在氧化物膜51上沉积具有N型半导体性质的催化物质52，并且构成氧化物膜51以保持P型半导体的性质。版权所有（C）2006，JPO＆NCIPI

5. 发明专利

JP2005195346A Corrosion reduction method for reactor structure material 有权
标题翻译：用于反应器结构材料的腐蚀减少方法
公开(公告)号：JP2005195346A
公开(公告)日：2005-07-21
申请号：JP2003435120
申请日：2003-12-26
申请人： Ishikawajima Harima Heavy Ind Co Ltd , Tokyo Electric Power Co Inc:The , Toshiba Corp , 東京電力株式会社 , 株式会社東芝 , 石川島播磨重工業株式会社
发明人： YAMAMOTO SEIJI , YOTSUYANAGI TADASHI , ICHIKAWA NAGAYOSHI , OSATO TETSUO , OKAMURA MASAHITO , TAKAGI JUNICHI , SUZUKI SHUNICHI , TAKAMORI KENRO , SHIBANO TAKESHI , HIRANO TAKASHI , FUKAYA YUICHI
IPC分类号： G21C19/307 , C23F20060101 , G21C3/07 , G21C3/20 , G21D1/00 , G21D3/08
CPC分类号： G21C9/00 , G21C3/324 , G21Y2002/103 , Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a corrosion reduction method for reactor structure materials by reducing an injection rate of hydrogen for preventing stress corrosion cracking, reducing transport of radioactivity to a turbine system and excess hydrogen quantity in off-gas system and resulting solution of metal oxide near noble metals due to adhesion of noble metals, corrosion of fuel materials and increase of hydrogen absorption.
SOLUTION: By injecting solution or suspension containing metal or metal compound which forms a material causing an exciting current by the effect of one or more of radiation, light and heat existing in a light water cooled reactor or under the reactor conditions, the material causing the exciting current on the reactor structure materials. Also, by injecting hydrogen into reactor cooling water and controlling hydrogen concentration in supply water, a corrosion electric potential is controlled in the corrosion reduction method for the reactor structure material.
COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：为了提供反应器结构材料的腐蚀降低方法，通过降低氢气的注入速率来防止应力腐蚀开裂，减少对涡轮机系统的放射性运输和废气系统中的过量氢气的产生，并导致贵金属附近金属氧化物附近的贵金属粘附，燃料物质腐蚀和氢吸收增加等问题。解决方案：通过注入含有金属或金属化合物的溶液或悬浮液，其形成通过存在于轻水冷却反应器中或在反应器条件下的一种或多种辐射，光和热的作用产生励磁电流的材料，导致反应堆结构材料上的励磁电流的材料。此外，通过将氢气注入反应器冷却水中并控制供水中的氢浓度，在反应器结构材料的腐蚀还原方法中控制腐蚀电位。版权所有（C）2005，JPO＆NCIPI

6. 发明专利

JP2014218729A ステンレス鋼の局部腐食抑制方法有权
标题翻译：不锈钢局部腐蚀抑制方法
公开(公告)号：JP2014218729A
公开(公告)日：2014-11-20
申请号：JP2013100597
申请日：2013-05-10
申请人：東京電力株式会社 , Tokyo Electric Power Co Inc:The
发明人： FUKAYA YUICHI , HIRASAKI TOSHIFUMI , KUMAGAI KATSUHIKO , TAKAMORI KENRO
IPC分类号： C23F11/18
CPC分类号： C23F11/18
摘要：【課題】効果的に局部腐食を抑制することができる化学種を用いた新たなステンレス鋼の局部腐食抑制方法を提供する。【解決手段】湿潤環境におけるステンレス鋼の局部腐食抑制方法であって、ステンレス鋼に接触する水分において、水分中に含まれる塩化物イオンのモル濃度に対して、0.1倍以上のモル濃度の亜硝酸イオンを共存させるステンレス鋼の局部腐食抑制方法。【選択図】なし
摘要翻译：要解决的问题：提供使用能够有效抑制局部腐蚀的化学物质的不锈钢局部腐蚀抑制方法。解决方案：提供在湿环境中使用的不锈钢局部腐蚀抑制方法，以及具有等于或相对于水分含有的氯离子的摩尔浓度，与与不锈钢接触的水含量共存超过0.1倍。

7. 发明专利

JP2006161114A Austenitic stainless steel material and weld joint thereof 审中-公开
标题翻译：奥氏体不锈钢材料及其焊接接头
公开(公告)号：JP2006161114A
公开(公告)日：2006-06-22
申请号：JP2004355615
申请日：2004-12-08
申请人： Sumitomo Metal Ind Ltd , Tokyo Electric Power Co Inc:The , 住友金属工業株式会社 , 東京電力株式会社
发明人： TAKEDA KIYOKO , OGAWA KAZUHIRO , ANADA HIROYUKI , KANZAKI MANABU , SUZUKI SHUNICHI , TAKAMORI KENRO , OKI TAKASHI
IPC分类号： C22C38/00 , B23K9/00 , B23K9/23 , B23K103/04 , C22C38/60
摘要： PROBLEM TO BE SOLVED: To provide an austenitic stainless steel material which can prevent stress corrosion cracking that occurs in a work hardened layer or a HAZ at the surface of a steel material used for equipment, a pipeline and the like in a nuclear power plant or the like, and to provide a weld joint thereof.
SOLUTION: (1) The austenitic stainless steel material comprises 0.10% or less C, 1.5% or less Si, 0.1-2.0% Mn, 20-35% Cr, 18-65% Ni, 0-3% Mo, 0.001-0.15% N, and the balance Fe with impurities among which P is 0.05% or less and S is 0.05% or less; and has a work-hardened layer in the surface layer harder than that in a wall center part by 50 or higher by Vickers hardness. (2) The weld joint of the austenitic stainless steel includes the austenitic stainless steel material having the above composition as a base metal and the work hardened layer and has the hardened layer in a welded heat affected zone in the surface of the base metal, which is harder than that of a wall center part of the base metal by 50 or higher by Vickers hardness.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供一种奥氏体不锈钢材料，其可以防止在用于设备，管道等的钢材表面的工作硬化层或HAZ中发生的应力腐蚀开裂发电厂等，并提供其焊接接头。（1）奥氏体不锈钢材料含有0.10％以下的C，1.5％以下的Si，0.1〜2.0％的Mn，20-35％的Cr，18-65％的Ni，0-3％的Mo， 0.001-0.15％N，余量为Fe，杂质为P为0.05％以下，S为0.05％以下。并且通过维氏硬度将表面层中的硬化层比壁中心部分的硬化层硬化50以上。（2）奥氏体不锈钢的焊接接头包括具有上述组成的奥氏体不锈钢材料作为基底金属和加工硬化层，并且在贱金属的表面的焊接热影响区域中具有硬化层，比维氏硬度的基础金属的壁中心部分的硬度要高50或更高。版权所有（C）2006，JPO＆NCIPI

8. 发明专利

JP2012032255A Nuclear power plant and method of hydrogen injection to nuclear reactor water supply 审中-公开
标题翻译：核动力装置和氢注射到核反应堆水供应的方法
公开(公告)号：JP2012032255A
公开(公告)日：2012-02-16
申请号：JP2010171394
申请日：2010-07-30
申请人： Tokyo Electric Power Co Inc:The , 東京電力株式会社
发明人： KOYABU KEN , TAKAMORI KENRO
IPC分类号： G21D1/00 , G21D3/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a nuclear power plant and a method of hydrogen injection to nuclear reactor water supply in which reduction of costs can be attained by decreasing the quantity of hydrogen to be used and the quantity of oxygen to be used by reducing the injection quantity of the excessive hydrogen without decreasing a dissolved hydrogen concentration.SOLUTION: A nuclear power plant 100 includes: a nuclear reactor 110; and a nuclear reactor water supply system (water supply path 134) for supplying water to the nuclear reactor. The nuclear power plant 100 further includes: a reservoir 142a that stores water; hydrogen supply means (hydrogen supply path 144) that supplies a hydrogen gas to the reservoir; hydrogen dissolving means (air bubble jetting device 146a and stirring device 148a) that is provided in the reservoir and dissolves the hydrogen gas in water to produce hydrogen dissolved water; and hydrogen dissolved water injection means (hydrogen dissolved water supply path 150) that supplies hydrogen dissolved water to the nuclear reactor water supply system.
摘要翻译：要解决的问题：提供一种核电厂和一种向核反应堆供水的氢气注入方法，通过减少使用的氢气量和使用的氧气量，可以实现成本降低通过减少过量氢的注入量而不降低溶解的氢浓度。解决方案：核电站100包括：核反应堆110; 以及用于向核反应堆供水的核反应堆供水系统（供水路径134）。核电站100还包括存储水的储存器142a; 向储存器供给氢气的氢供给装置（氢供给路径144）氢气溶解装置（气泡喷射装置146a和搅拌装置148a），其设置在储存器中并将氢气溶解在水中以产生氢溶解的水; 以及将氢溶解水供应到核反应堆供水系统的氢溶解水注入装置（氢溶解水供给路径150）。版权所有（C）2012，JPO＆INPIT

9. 发明专利

JP2009079240A Austenitic stainless steel and producing method therefor, and structural material and piping in nuclear reactor 审中-公开
标题翻译：奥氏体不锈钢及其制造方法，以及核反应堆中的结构材料和管道
公开(公告)号：JP2009079240A
公开(公告)日：2009-04-16
申请号：JP2007247747
申请日：2007-09-25
申请人： Tohoku Univ , Tokyo Electric Power Co Inc:The , 国立大学法人東北大学 , 東京電力株式会社
发明人： YONEZAWA TOSHIO , SUZUKI SHUNICHI , TEZUKA HIDESHI , TAKAMORI KENRO , OKI TAKASHI
IPC分类号： C22C38/00 , C21D8/00 , C22C38/44 , C22C38/50 , G21C5/00 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide an austenitic stainless steel which is made hardly sensible and has excellent stress-corrosion cracking resistance, and even when the stress-corrosion crack is caused, hardly causes propagation of the stress-corrosion crack, since it has high stacking-fault energy value, and a producing method therefor, and the structural material thereof.
SOLUTION: The austenitic stainless steel is composed of, by wt.%, ≤0.030% C, ≤0.030% N, ≤0.1% Si, ≤1.0% Mn, 10-26% Ni, 15-30% Cr, ≤3.0% Mo and the balance substantially Fe with inevitable impurities, wherein solid-solution content of C is ≤0.010% and solid-solution content of N is ≤0.010%. Further, the constitution containing 0.01-2.0% Al and the constitution containing ≤1.0% one or more kinds selected from V, Ti and Nb can be adopted.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：为了提供几乎不敏感并且具有优异的耐应力腐蚀开裂性的奥氏体不锈钢，并且即使当引起应力腐蚀裂纹时，也几乎不会引起应力腐蚀裂纹的扩展，因为它具有高堆垛层错能量值及其制造方法及其结构材料。
解决方案：奥氏体不锈钢以重量％，≤0.030％C，≤0.030％N，≤0.1％Si，≤1.0％Mn，10-26％Ni，15-30％Cr， ≤3.0％Mo，余量基本为Fe，不可避免的杂质，其中C的固溶含量≤0.010％，N的固溶含量≤0.010％。此外，可以采用包含0.01-2.0％的Al和包含≤1.0％的选自V，Ti和Nb中的一种或多种的构成。版权所有（C）2009，JPO＆INPIT

10. 发明专利

JP2006159262A Welded joint and welding material 审中-公开
标题翻译：焊接接头和焊接材料
公开(公告)号：JP2006159262A
公开(公告)日：2006-06-22
申请号：JP2004355614
申请日：2004-12-08
申请人： Sumitomo Metal Ind Ltd , Tokyo Electric Power Co Inc:The , 住友金属工業株式会社 , 東京電力株式会社
发明人： OGAWA KAZUHIRO , TAKEDA KIYOKO , KOUSU TAKAHIRO , ANADA HIROYUKI , SUZUKI SHUNICHI , TAKAMORI KENRO , OKI TAKASHI
IPC分类号： B23K35/30 , B23K9/00 , B23K9/23 , B23K103/04 , C22C38/00 , C22C38/58
摘要： PROBLEM TO BE SOLVED: To provide a welded joint in which a weld metal has excellent stress corrosion cracking resistance, and to provide a welding material suitably used for producing the same.
SOLUTION: The austenitic weld metal has a composition comprising, by mass, ≤0.03% C, ≤1.0% Si, 0.1 to 2.0% Mn, 15 to 22% Cr, 8 to 12% Ni, 0 to 3% Mo and 0.001 to 0.15% N, and the balance Fe with impurities, and, in the impurities, the content of P is ≤0.04% and the content of S is 0.03%, and further, the value of FP expressed by following formula (1) lies in the range from -3 to 0: formula (1) is FP=Ni+30C+20N+0.5Mn-1.1Cr-1.32Mo-1.65Si+9 (1); wherein, the atomic symbols in formula denote the content (mass%) of each element. The welded joint is suitably used in a high temperature pure water environment of nuclear power generation equipment.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：提供焊接金属具有优异的抗应力腐蚀开裂性的焊接接头，并提供适合用于制造焊接材料的焊接材料。解决方案：奥氏体焊接金属具有以质量％计含有0.03％C，≤1.0％Si，0.1％至2.0％Mn，15％至22％Cr，8％至12％Ni，0％至3％Mo 和0.001〜0.15％的N，余量为Fe的杂质，杂质中的P含量为0.04％以下，S含量为0.03％，另外，由下式（1）表示的FP值）在-3至0的范围内：公式（1）为FP = Ni + 30C + 20N + 0.5Mn-1.1Cr-1.32Mo-1.65Si + 9（1）; 其中，式中的原子符号表示各元素的含量（质量％）。焊接接头适用于核能发电设备的高温纯水环境。版权所有（C）2006，JPO＆NCIPI

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