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1. 发明专利

JP2006275620A Accelerated corrosiveness test method for component material made of zirconium alloy for boiling water reactor 有权
标题翻译：用于沸腾水反应器的锆合金组分材料的加速腐蚀性测试方法
公开(公告)号：JP2006275620A
公开(公告)日：2006-10-12
申请号：JP2005092151
申请日：2005-03-28
申请人： Tokyo Electric Power Co Inc:The , Zirco Products Co Ltd , 東京電力株式会社 , 株式会社ジルコプロダクツ
发明人： ISHII YOSHIAKI , HAGI SHIGEKI , TAKEDA KIYOKO , HARADA MAKOTO
IPC分类号： G21C17/06 , G01N17/00 , G21C5/00
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a method for evaluating intra-reactor corrosiveness of a component member or element such as a fuel cladding pipe made of zirconium alloy used in a nuclear reactor, and in particular in a BWR, by a relatively simple and safe means, outside the reactor, in a short period of time, without using radiation exposure.
SOLUTION: This corrosiveness test method is for a component material made of zirconium alloy used for a boiling water reactor. In this accelerated corrosiveness test method for the component material made of zirconium alloy used for the boiling water reactor, a test material of the component material is immersed for corrosiveness evaluation in supercritical water with its dissolved oxygen concentration adjusted to be not less than 0.1 ppb and less than 10 ppb for a prescribed period of time.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种用于评价在核反应堆中特别是在BWR中使用的由锆合金制成的燃料包层管的组分构件或元件的反应堆内腐蚀性的方法，简单安全的手段，在反应堆外，在短时间内，不用辐射照射。
解决方案：该腐蚀性试验方法是用于沸水反应器的锆合金制成的部件材料。在用于沸水反应器的由锆合金制成的部件材料的这种加速腐蚀性试验方法中，将成分材料的试验材料浸入超临界水中进行腐蚀性评价，其溶解氧浓度调节至不低于0.1ppb，在规定的时间内少于10 ppb。版权所有（C）2007，JPO＆INPIT

2. 发明专利

JP4968834B2 Discrimination apparatus and method for determining fuel rod cladding material 有权
公开(公告)号：JP4968834B2
公开(公告)日：2012-07-04
申请号：JP2007076244
申请日：2007-03-23
申请人：原子燃料工業株式会社 , 株式会社ジルコプロダクツ
发明人：哲也塩田 , 利行木村 , 徳興阿保 , 秀明阿部
IPC分类号： G21C17/06 , G01R27/02

3. 发明专利

JP4615134B2 High strength and Zr alloy reactor fuel cladding tubes having excellent corrosion resistance 有权
公开(公告)号：JP4615134B2
公开(公告)日：2011-01-19
申请号：JP2001079734
申请日：2001-03-21
申请人：三菱マテリアル株式会社 , 三菱重工業株式会社 , 原子燃料工業株式会社 , 株式会社ジルコプロダクツ
发明人：琢弥村井 , 毅磯部
IPC分类号： C22C16/00 , G21C3/07
CPC分类号： Y02E30/40

4. 发明专利

JP2008232985A Device and method for discriminating fuel rod cladding pipe material 有权
标题翻译：用于分离燃油管道密封管材料的装置和方法
公开(公告)号：JP2008232985A
公开(公告)日：2008-10-02
申请号：JP2007076244
申请日：2007-03-23
申请人： Nuclear Fuel Ind Ltd , Zirco Products Co Ltd , 原子燃料工業株式会社 , 株式会社ジルコプロダクツ
发明人： ABO NORIOKI , SHIODA TETSUYA , KIMURA TOSHIYUKI , ABE HIDEAKI
IPC分类号： G21C17/06 , G01R27/02
摘要： PROBLEM TO BE SOLVED: To discriminate the material of a cladding pipe without requiring labor hour and time during manufacturing of a fuel rod.
SOLUTION: This discrimination device of fuel rod cladding pipe material has a conductivity measuring means. This discrimination device of fuel rod cladding pipe material has a temperature keeping means for keeping the temperature of a measurement part when the conductivity is measured. The conductivity measuring means has a pedestal where a fuel rod cladding pipe is placed at a predetermined position, a probe, a contact adjusting section for bringing the probe into contact with the fuel rod cladding pipe in a certain condition, and a conductivity measuring section for measuring the conductivity based on an electric signal from the probe in a state where the tip of the probe is in contact with the fuel rod cladding pipe placed at the predetermined position on the pedestal in the certain condition under action of the contact adjusting section.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：在燃料棒的制造过程中不需要劳动时间和时间来区分包层管的材料。解决方案：燃料棒包层管材的鉴别装置具有电导率测量装置。燃料棒包层管材的鉴别装置具有用于在测量电导率时保持测量部件的温度的温度保持装置。电导率测量装置具有将燃料棒包覆管放置在预定位置的基座，探针，用于使探针在一定条件下与燃料棒包层管接触的接触调节部，以及电导率测定部，在接触调节部的作用下，在一定的状态下，在探针的前端与放置在基座上的预定位置的燃料棒包层管接触的状态下，基于来自探针的电信号，测定导电率。版权所有（C）2009，JPO＆INPIT

5. 发明专利

JP3483804B2 Method of manufacturing a corrosion-resistant zirconium-based alloy tube 有权
公开(公告)号：JP3483804B2
公开(公告)日：2004-01-06
申请号：JP18901399
申请日：1999-07-02
申请人：原子燃料工業株式会社 , 株式会社ジルコプロダクツ
发明人：俊靖宮下 , 茂樹萩
IPC分类号： G21C3/07 , C22C16/00 , C22F1/00 , C22F1/18
CPC分类号： Y02E30/40

6. 发明专利

JP4761803B2 Corrosion accelerated test method of boiling water reactor for the zirconium alloy construction material 有权
公开(公告)号：JP4761803B2
公开(公告)日：2011-08-31
申请号：JP2005092151
申请日：2005-03-28
申请人：東京電力株式会社 , 株式会社ジルコプロダクツ
发明人：誠原田 , 良明石井 , 貴代子竹田 , 茂樹萩
IPC分类号： G21C17/06 , G01N17/00 , G21C5/00
CPC分类号： Y02E30/40

7. 发明专利

JP2003277859A Zirconium alloy having excellent corrosion resistance and production method therefor 审中-公开
标题翻译：具有优良耐腐蚀性的锆合金及其生产方法
公开(公告)号：JP2003277859A
公开(公告)日：2003-10-02
申请号：JP2002076568
申请日：2002-03-19
申请人： Zirco Products Co Ltd , 株式会社ジルコプロダクツ
发明人： TAKEDA KIYOKO , HARADA MAKOTO
IPC分类号： G21C3/06 , C22C16/00 , C22F1/00 , C22F1/18 , G21C3/07
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To provide a zirconium alloy which is provided with sufficient nodular corrosion resistance and uniform corrosion resistance meeting the tendency of the elongation of the residence period of nuclear fuel in a reactor accompanying increase in the combustion degree thereof, and is suitable for a nuclear fuel cladding tube and a nuclear fuel structural member, and to provide a production method therefor.
SOLUTION: The zirconium alloy having excellent corrosion resistance comprises, by mass, 0.8 to 1.4% Sn, 0.15 to 0.45% Fe, 0.05 to 0.30% Cr, 0.01 to 0.15% Ni and >0.006 to 0.020% Si, and the balance Zr with inevitable impurities, and in which the incorporation ratios of Fe, Cr and Ni satisfy the following two inequalities: 0.9≤Fe/Cr≤8 (1), and 2.5≤Fe/Ni≤25 (2).
COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：提供一种锆合金，其具有足够的耐结晶腐蚀性和均匀的耐腐蚀性，满足核燃料在反应器中随着其燃烧程度的增加而延长的停留期延长的倾向;以及适用于核燃料包层管和核燃料结构构件，并提供其制造方法。＆lt;解决方案＆gt;具有优异的耐腐蚀性的锆合金，其中Sn为0.8〜1.4％，Fe为0.15〜0.45％，Cr为0.05〜0.30％，Ni为0.01〜0.15％，Si为0.006〜0.020％平衡Zr与不可避免的杂质，其中Fe，Cr和Ni的掺入比满足以下两个不等式：0.9≤Fe/Cr≤8（1），2.5≤Fe/Ni≤25（2）。版权所有（C）2004，JPO

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