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1. 发明专利

JP2013170882A Method and apparatus for repairing nuclear equipment 审中-公开
标题翻译：修理核设备的方法和装置
公开(公告)号：JP2013170882A
公开(公告)日：2013-09-02
申请号：JP2012034067
申请日：2012-02-20
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , ITAYA MASAO , SUZUKI ATSUSHI , ABURA AKINORI , SATO KATSUHIKO
IPC分类号： G21C19/02 , G21C19/20
摘要： PROBLEM TO BE SOLVED: To repair a leaking part which is generated in nuclear equipment in a severe accident or the like, in a short time.SOLUTION: A repair method includes a first step for identifying a leaking part 9a in nuclear equipment within a reactor pressure vessel, a second step for selecting a piping line 16 to be connected to a repair material supply device 30, a third step for connecting the selected piping line 16 and the repair material supply device 30, and a fourth step for supplying a repair material 24 from the repair material supply device 30 through the piping line 16 to the leaking part 9a.
摘要翻译：要解决的问题：在短时间内修复在严重事故等中的核设备中产生的泄漏部分。解决方案：修复方法包括用于识别反应堆内的核设备中的泄漏部分9a的第一步骤压力容器，用于选择要连接到修补材料供应装置30的管道16的第二步骤，用于连接所选择的管道16和修理材料供应装置30的第三步骤，以及用于提供修理材料的第四步骤 24从维修材料供给装置30经由配管16到泄漏部9a。

2. 发明专利

JP2013079844A Nuclear reactor containment and anticorrosive coating method for nuclear reactor containment 审中-公开
标题翻译：用于核反应堆容器的核反应堆容纳和抗腐蚀涂层方法
公开(公告)号：JP2013079844A
公开(公告)日：2013-05-02
申请号：JP2011219235
申请日：2011-10-03
申请人： Toshiba Corp , 株式会社東芝
发明人： KUBO TATSUYA , KAWANO SHOHEI
IPC分类号： G21D1/00 , G21C13/00 , G21C13/08
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To improve soundness of a nuclear reactor containment and equipment installed in the nuclear reactor containment including a nuclear pressure vessel, piping and other various devices in emergency cooling, by applying anticorrosive coating to the nuclear reactor containment and/or the equipment to prevent corrosion caused by flooding of cooling water.SOLUTION: In an anticorrosive coating method for a nuclear reactor containment 1 to coat with an anticorrosive metallic material at at least a part of the inner wall of the nuclear reactor containment 1 and/or a part of the surfaces of various pieces of equipment in the nuclear reactor containment 1, the corrosion potential of the coating metallic material is higher than the corrosion potential(s) of metallic material(s) of the inner wall of the nuclear reactor containment and/or the various pieces of equipment in it to be coated.
摘要翻译：要解决的问题：为了提高安装在包括核压力容器，管道和其他各种紧急冷却装置在内的核反应堆安全壳体中的核反应堆安全壳和设备的稳定性，通过将抗腐蚀涂层应用于核反应堆遏制和/ 或设备，以防止冷却水淹没引起的腐蚀。解决方案：在用于核反应堆容器1的防腐涂层方法中，用于在核反应堆容器1的内壁的至少一部分和/或一部分表面的一部分表面上涂覆防锈金属材料核反应堆容器中的设备1，涂层金属材料的腐蚀电位高于核反应堆容器内壁和/或其内的各种设备的金属材料的腐蚀电位被涂。版权所有（C）2013，JPO＆INPIT

3. 发明专利

JP2009144191A Method for manufacturing high corrosion-resistant material, and nuclear reactor structural material 审中-公开
标题翻译：制造高耐腐蚀材料的方法和核反应堆结构材料
公开(公告)号：JP2009144191A
公开(公告)日：2009-07-02
申请号：JP2007321121
申请日：2007-12-12
申请人： Toshiba Corp , 株式会社東芝
发明人： OBATA MINORU , KAWANO SHOHEI , KANO FUMIHISA , SAITO YOSHIHISA , ABE YUMIKO
IPC分类号： C21D8/00 , G21D1/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method with which a corrosion-resistant material having high stress corrosive crack restraining effect, can be easily manufactured.
SOLUTION: To a material to be treated, a strain is generated by loading the stress equal to or smaller than the proof stress of the material to be treated in the following heat-treatment temperature. Successively, under the state of generating the strain to the material to be treated, the material to be treated is heated to the heat-treatment temperature and held for a prescribed time. Thus, the high corrosion resistant material is obtained by applying the heat-treatment to the material to be treated.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：提供可以容易地制造具有高应力腐蚀裂纹抑制效果的耐腐蚀材料的方法。解决方案：对于要处理的材料，通过将等于或小于待处理材料的试样应力的应力加载到随后的热处理温度中来产生应变。接着，在对待处理材料产生应变的状态下，将待处理的材料加热至热处理温度并保持规定时间。因此，通过对待处理的材料进行热处理，可获得高耐蚀材料。版权所有（C）2009，JPO＆INPIT

4. 发明专利

JP2007232463A Weld part evaluation system for nuclear reactor structure, its evaluation method, and program 审中-公开
标题翻译：用于核反应堆结构的焊接部分评估系统，其评估方法和程序
公开(公告)号：JP2007232463A
公开(公告)日：2007-09-13
申请号：JP2006052256
申请日：2006-02-28
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , TANAKA SHIGEAKI , SAKAMOTO HIROSHI
IPC分类号： G21C17/003 , B23K31/00 , G01N17/00
摘要： PROBLEM TO BE SOLVED: To evaluate the joint strength of a weld part after welding a nuclear reactor structure irradiated with neutrons.
SOLUTION: This weld part evaluation system comprises a grain boundary disposition calculation means 12 at least modeling the disposition of crystal grain boundaries of the nuclear reactor structure based on the crystal grain size of the reactor structure, a time history calculation means 13 calculating time histories on temperature, stress, and strain at an optional point in the vicinity of a weld during welding based on its shape and welding conditions, a He bubble diameter/density calculation means 14 severally calculating the diameters and density of He bubbles on a plurality of grain boundaries in the vicinity of the weld based on the time histories on the calculated temperature and stress and on a He content, a crack occurrence determination means 15 severally determining crack occurrence on the plurality of grain boundaries in the vicinity of a weld metal from the calculated bubble diameters and density, and from the time history of the stain, an index calculation means 17 calculating a crack index for the vicinity of the weld metal from determined grain boundary crack occurrence distribution, and a strength prediction means 18 predicting the strength of the weld part based on the calculated crack index.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：评估在焊接用中子照射的核反应堆结构之后焊接部分的接合强度。解决方案：该焊接部分评估系统包括晶界配置计算装置12，其至少基于反应堆结构的晶粒尺寸来模拟核反应堆结构的晶粒边界的布置，时间历史计算装置13计算基于其形状和焊接条件，焊接期间焊接附近的可选点处的温度，应力和应变的时间历程，He气泡直径/密度计算装置14分别计算多个He气泡的直径和密度基于计算出的温度和应力的时间历程和He含量的焊缝附近的晶界的裂纹发生确定装置15，分别确定焊接金属附近的多个晶界处的裂纹发生，计算的气泡直径和密度，以及根据染色的时间历程，指数计算装置17 cal 根据确定的晶界裂纹发生分布来计算焊缝金属附近的裂纹指数;以及强度预测装置18，其根据计算出的裂纹指数预测焊接部分的强度。版权所有（C）2007，JPO＆INPIT

5. 发明专利

JP2007225387A Method for predicting fatigue property in weld zone of reactor structure and system and program for such method 审中-公开
标题翻译：用于预测反应器结构焊接区域的疲劳性能的方法及其方法
公开(公告)号：JP2007225387A
公开(公告)日：2007-09-06
申请号：JP2006045571
申请日：2006-02-22
申请人： Toshiba Corp , 株式会社東芝
发明人： HAYASHI TAKAHIRO , KAWANO SHOHEI , TANAKA SHIGEAKI
IPC分类号： G21C17/00 , G21C5/00 , G21C17/003 , G21C19/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method for predicting fatigue properties in a weld zone in a reactor structure which enables the precise prediction of the fatigue properties in the weld zone in the reactor structure irradiated with a neutron beam.
SOLUTION: The method 10 for predicting the fatigue properties includes: a time history calculation step 11 for calculating the time history of the temperature, stress and distortion during welding on the basis of the contour of the reactor structure 21 and welding conditions; a computation step 12 for computing the diameter and density of He bubbles on the grain boundary 24 in the vicinity of the weld zone 23 on the basis of the time history of temperature and stress and the He content of the reactor structure 21; and a judgment step 13 for judging the occurrence of an intercrystalline crack 26 on the basis of the diameter and density of the He bubbles and the time history of distortion. Next, in a defect index calculation step 14, a defect index of the grain boundary 24 is calculated on the basis of the diameter and density of the He bubbles and the occurrence or nonoccurrence of the intercrystalline crack 26. In a prediction step 15, the fatigue properties are predicted on the basis of the defect index calculated in the step 14.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种用于预测反应堆结构中的焊接区域中的疲劳性能的方法，其能够精确地预测在用中子束照射的反应堆结构中的焊接区域中的疲劳性能。解决方案：用于预测疲劳性能的方法10包括：时间历史计算步骤11，用于基于反应堆结构21的轮廓和焊接条件来计算焊接期间的温度，应力和变形的时间历程; 计算步骤12，用于基于温度和应力的时间历程和反应堆结构21的He含量来计算焊接区23附近的晶界24上的He气泡的直径和密度; 以及用于基于He气泡的直径和密度以及变形的时间历程来判断晶间裂纹26的发生的判断步骤13。接下来，在缺陷指标计算步骤14中，基于He气泡的直径和密度以及晶间裂纹26的发生或不发生来计算晶界24的缺陷指数。在预测步骤15中，基于步骤14中计算的缺陷指数来预测疲劳性能。版权所有（C）2007，JPO＆INPIT

6. 发明专利

JP2005213618A Method and device for modifying surface of structure 审中-公开
标题翻译：用于修改结构表面的方法和装置
公开(公告)号：JP2005213618A
公开(公告)日：2005-08-11
申请号：JP2004024005
申请日：2004-01-30
申请人： Toshiba Corp , 株式会社東芝
发明人： OBATA MINORU , KAWANO SHOHEI , SAITO YOSHIHISA , YAMAMOTO TETSUO , ISHIWATARI YUTAKA
IPC分类号： C21D1/10 , C21D9/00
CPC分类号： Y02P10/253
摘要： PROBLEM TO BE SOLVED: To provide a method and a device for modifying a surface of a structure capable of efficiently and reliably preventing occurrence of damages by modifying the surface by material improvement of an execution part through a solution treatment and by compressive stress through stress improvement. SOLUTION: The method for modifying the surface of the structure comprises a solution treatment step of heating the surface of an execution part of the structure at a temperature in the range of ≥ 900°C and ≤ 1,100°C by the high frequency induction heating, and a step of controlling the average cooling rate to be ≥ 30°C/sec when lowering the temperature of the surface of the execution part to 300°C from the solution treatment temperature. COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：解决问题的方案和装置：通过溶解处理和压缩应力，通过改进执行部件的材料改性来改进能够有效且可靠地防止损伤发生的结构的表面的方法和装置通过压力改善。解决方案：用于改变结构表面的方法包括：溶液处理步骤，其在≥900℃和≤11100℃的温度范围内以高频加热该结构的执行部分的表面感应加热，以及当将所述执行部件的表面的温度从所述固溶处理温度降低至300℃时，将所述平均冷却速度控制在≥30℃/秒的步骤。版权所有（C）2005，JPO＆NCIPI

7. 发明专利

JP2005003370A Diagnostic method and device of member exposed to neutron irradiation 有权
标题翻译：诊断方法和暴露于中性辐射的成员设备
公开(公告)号：JP2005003370A
公开(公告)日：2005-01-06
申请号：JP2003163581
申请日：2003-06-09
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , TANAKA SHIGEAKI , SAKAMOTO HIROSHI
IPC分类号： G01N33/00 , G01N3/40 , G01N33/20 , G21C17/00 , G21C17/003
摘要： PROBLEM TO BE SOLVED: To provide a diagnostic method and a device capable of evaluating accurately a damage of a member exposed to neutron irradiation by collection of a sample having the size exerting no influence on the function of the member. SOLUTION: This method has a constitution equipped with a sample collection process S1 for collecting the sample 3 from an evaluation object portion of the member 1 comprising a stainless steel or a nickel-based alloy and receiving the neutron irradiation, a sample processing process S2 for processing the sample to have a measurable shape, a hardness measuring process S3 for indenting a hardness measuring indenter into the surface to be measured of the sample, and determining the relation between the indentation depth and an indentation load, an analysis process S4 for determining the relation between the hardness and the indentation load from the relation between the measured indentation depth and the indentation load, and an evaluation process S5 for evaluating a mechanical characteristic of the evaluation object portion from the relation between the hardness and the indentation load. COPYRIGHT: (C)2005,JPO&NCIPI
摘要翻译：要解决的问题：提供一种诊断方法和装置，其能够通过收集对该构件的功能没有影响的尺寸的样品进行准确评估暴露于中子照射的构件的损伤。解决方案：该方法具有配备有样品收集过程S1的结构，用于从包含不锈钢或镍基合金的构件1的评估对象部分收集样品3并接收中子照射，样品处理用于处理样品以具有可测量形状的工艺S2，用于将测量压痕的硬度测量压头压入待测试的表面的硬度测量过程S3，以及确定压痕深度和压痕负载之间的关系，分析过程S4 用于根据测量的压痕深度和压痕负载之间的关系确定硬度和压痕负载之间的关系，以及用于根据硬度和压痕负载之间的关系来评估评估对象部分的机械特性的评估过程S5。版权所有（C）2005，JPO＆NCIPI

8. 发明专利

JP2015052558A 溶融核燃料物質の搬出管理方法审中-公开
标题翻译：执行和管理熔炼核燃料材料的方法
公开(公告)号：JP2015052558A
公开(公告)日：2015-03-19
申请号：JP2013186325
申请日：2013-09-09
申请人：株式会社東芝 , Toshiba Corp
发明人： KAWANO SHOHEI , HAYASHI YAMATO , MORI ATSUSHI , SUZUKI ATSUSHI
IPC分类号： G21F9/00 , G21C17/06 , G21F9/30
摘要：【課題】溶融核燃料物質の搬出工程で、溶融核燃料物質に含まれるウラン235の含有率を簡便に解析し、再臨界を評価・管理する方法を提供する。【解決手段】溶融核燃料物質を昇降装置の端部に取り付けられた採取工具により採取する工程ステップ1と、採取した溶融核燃料物質の水中重量W1及び気中重量W2を測定する工程ステップ2、3と、炉心に装荷された核燃料物質の密度D0及びウラン235含有率U0と前記測定された水中重量W1及び気中重量W2とから前記採取した溶融核燃料物質中のウラン235含有率を算出する工程ステップ4と、前記算出されたウラン235含有率から前記溶融核燃料物質の再臨界を評価する工程ステップ5とを、有する。【選択図】図2
摘要翻译：要解决的问题：提供一种能够容易地分析在熔化的核燃料材料的执行步骤期间熔化的核燃料材料中包含的铀235的含有率以评估和管理重新生产的方法。解决方案：在步骤1中，a 使用附接到升降机的尖端的拾取工具拾取熔化的核燃料材料。在步骤2和3中，测量所拾取的熔融核燃料材料的水下重量W1和空气W2中的重量。在步骤4中，通过使用密度D0和安装在反应堆堆芯中的核燃料材料的铀235的含有率U0和测量的水下重量W1来计算拾取的熔融核燃料材料中所含的铀235的含有率并在空气中的重量W2中拾取熔化的核燃料材料。在步骤5中，通过使用计算的铀235含量率来评估熔化的核燃料材料的重新连接性。

9. 发明专利

JP2009191341A Austenitic stainless steel member, method for manufacturing austenitic stainless steel member, and nuclear reactor member 审中-公开
标题翻译：奥氏体不锈钢构件，制造奥氏体不锈钢构件的方法和核反应堆构件
公开(公告)号：JP2009191341A
公开(公告)日：2009-08-27
申请号：JP2008035809
申请日：2008-02-18
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , OBATA MINORU , ITO KIICHI , TANAKA SHIGEAKI
IPC分类号： C21D8/00 , C22C38/00
摘要： PROBLEM TO BE SOLVED: To provide an austenitic stainless steel member especially excellent in stress-corrosion cracking resistance in furnace water, and a nuclear reactor member using the same.
SOLUTION: Cold working is applied to the surface of the austenitic stainless steel sheet, and in the thickness direction thereof, the austenitic stainless worked steel sheet having strain distribution such that strain on the surface of this steel sheet is larger than that at the center part thereof, is formed. A heat-treatment is applied to this worked steel sheet at the temperature of 900-950°C to obtain the austenitic stainless steel member.
COPYRIGHT: (C)2009,JPO&INPIT

10. 发明专利

JP2009030991A Method, system and program for evaluating weld crack 审中-公开
标题翻译：用于评估焊接裂纹的方法，系统和程序
公开(公告)号：JP2009030991A
公开(公告)日：2009-02-12
申请号：JP2007192131
申请日：2007-07-24
申请人： Toshiba Corp , 株式会社東芝
发明人： KAWANO SHOHEI , ITO KIICHI , TANAKA SHIGEAKI
IPC分类号： G21C17/003
摘要： PROBLEM TO BE SOLVED: To find the distribution of weld cracks in the vicinity of a weld zone in a reactor structure welded through two or more paths after irradiating the structure with neutrons.
SOLUTION: The locations of grain boundaries in the vicinity of the weld zone are modelled on the basis of crystal grain sizes in the reactor structure (Step S1). The time history of the temperature, stress and distortion at any given point in the vicinity of the weld metal during welding for each welding path is calculated on the basis of the geometry and welding conditions of the reactor structure (Step S2). The diameter and density of He bubbles on the crystalline boundaries in the vicinity of the weld zone are calculated for each welding paths on the basis of the time history of the temperature and stress for each welding path and the He content in the reactor structure(Step S3). It is judged on the basis of the diameter and density of the He bubbles and the time history of distortion whether cracks appear on the grain boundaries or not (Step S4). The distribution of weld cracks appearing in the vicinity of the weld zone is found on the basis of the result of the judgement (Step S5).
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：通过在用中子照射结构之后通过两个或更多个路径焊接的反应堆结构中的焊接区附近找到焊缝裂纹的分布。解决方案：基于反应器结构中的晶粒尺寸对焊接区附近的晶界位置进行建模（步骤S1）。基于反应器结构的几何形状和焊接条件，计算出每个焊接路径的焊接期间焊接金属附近的任何给定点处的温度，应力和变形的时间历程（步骤S2）。基于每个焊接路径的温度和应力的时间历程和反应堆结构中的He含量，计算焊接区附近的结晶边界上的He的直径和密度在每个焊接路径上的步骤（步骤 S3）。基于He气泡的直径和密度以及晶界上是否出现裂纹的变形时间历程进行判断（步骤S4）。基于判断结果，找到焊接区附近出现的焊缝裂纹分布（步骤S5）。版权所有（C）2009，JPO＆INPIT

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