会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 3. 发明专利
    • Joined structure of cobalt-based alloy
    • 基于钴的合金的接合结构
    • JP2003048076A
    • 2003-02-18
    • JP2001235707
    • 2001-08-03
    • Hitachi Ltd株式会社日立製作所
    • KIYOTOKI YOSHIHISACHIKAZAKI MITSUOMATSUSHITA SHIZUOKUNIYA JIROKATO TAKAHIKOCHIBA YOSHITERU
    • G21D1/00B23K20/00B23K35/30B23K103/08C22C19/07F16K25/00G21D1/02
    • G21D1/02Y02E30/40Y10T137/7036Y10T428/12861Y10T428/12931Y10T428/12937
    • PROBLEM TO BE SOLVED: To improve the corrosion resistance and wear resistance of a cobalt- based alloy part in a joined structure of a cobalt-based alloy. SOLUTION: In the joined structure of a cobalt-based alloy, a cobalt-based alloy layer 1 where granular or aggregated eutectic carbide particles 2 are dispersed is joined to the metal of a base material 37 via an insert material layer 36. The joined structure of the cobalt-based alloy is obtained by; interposing an insert material having a thickness of about 40 μm into the space between the base material of S45C carbon steel and a cobalt-based alloy material which has a composition containing, by weight, 1.03% C, 29.73% Cr, 3.86% W, 2.59% Ni, 2.67% Fe, 0.59% Si and 0.07% Mo, and the balance substantially Co and which contains granular or aggregated eutectic carbide particles having a particle size of
    • 要解决的问题:提高钴基合金的接合结构中的钴基合金部件的耐腐蚀性和耐磨性。 解决方案:在钴基合金的接合结构中,分散有颗粒或聚集的共晶碳化物颗粒2的钴基合金层1通过插入材料层36接合到基材37的金属。接合结构 的钴基合金通过以下方式得到: 将具有约40μm厚度的插入材料插入到S45C碳钢的基材和钴基合金材料之间的空间中,所述钴基合金材料具有重量比为1.03%C,29.73%Cr,3.86%W的组成, 2.59%Ni,2.67%Fe,0.59%Si和0.07%Mo,余量基本上为Co,并且在铸造结构的基体中含有粒径<=30μm的粒状或聚集的共晶碳化物颗粒; 并在1,100℃进行液相扩散接合1小时的保持时间。 接合后的钴系合金层1含有粒状或聚集的共晶碳化物。
    • 4. 发明专利
    • Highly corrosion-resistant reactor core material
    • 高抗腐蚀反应堆核心材料
    • JP2007031803A
    • 2007-02-08
    • JP2005219864
    • 2005-07-29
    • Hitachi Ltd株式会社日立製作所
    • KASAHARA SHIGEKIKUNIYA JIROMATSUURA MASAYOSHI
    • C22C38/00C21D6/00C22C38/58G21C5/00G21D1/00
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a highly corrosion-resistant reactor core material having excellent corrosion resistance, swelling resistance and stress corrosion cracking resistance under radiation exposure and under a high-temperature and high-pressure water environment.
      SOLUTION: As a member subjected to neutron irradiation in high-temperature water, austenitic steel containing at least either of Ti and Zr is used. To be concrete, the steel has a composition consisting of 0.005 to 0.04% C, ≤1% Si, ≤2% Mn, 23 to 28% Cr, 16 to 25% Ni, 0.5 to 3% Mo, 0.1 to 2% of at least either of Ti and Zr and the balance ≥50% Fe and further containing, other than the above, 1.0%, in total, of at least one or more elements among Pd, Pt and Hf. The steel is used as a constituent material for a reactor core of a nuclear reactor.
      COPYRIGHT: (C)2007,JPO&INPIT
    • 要解决的问题:提供耐辐射暴露和高温高压水环境下具有优异的耐腐蚀性,抗溶胀性和耐应力腐蚀开裂性的高耐腐蚀性的反应堆芯材。 解决方案:作为在高温水中进行中子照射的构件,使用含有Ti和Zr中的至少一种的奥氏体钢。 具体而言,钢的组成为:含有0.005〜0.04%的C,≤1%的Si,≤2%的Mn,23〜28%的Cr,16〜25%的Ni,0.5〜3%的Mo,0.1〜2% Ti和Zr中的至少一种,余量≥50%的Fe,除了上述以外,还含有Pd,Pt和Hf中至少一种或多种元素的1.0%。 钢被用作核反应堆的反应堆核心的构成材料。 版权所有(C)2007,JPO&INPIT
    • 5. 发明专利
    • Manufacturing method of nuclear/thermal power plant valve device
    • 核/热电厂阀门装置的制造方法
    • JP2003028315A
    • 2003-01-29
    • JP2001220810
    • 2001-07-23
    • Hitachi Ltd株式会社日立製作所
    • CHIKAZAKI MITSUOKUNIYA JIROKIYOTOKI YOSHIHISASAKAMOTO AKIRACHIBA YOSHITERUMATSUSHITA SHIZUO
    • G21D1/00C22C19/07F16K1/20F16K5/02
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a valve having excellent corrosion/erosion resistance and maintainability by joining corrosion/wearing resisting alloy wherein eutectic carbide is discontinuously distributed to a sliding portions of various apparatus and valves by brazing, to improve the maintainability of thermal power plant and a nuclear power plant, and to provide the nuclear power plant being excellent in the safety of work and having a system for circulating primary cooling water. SOLUTION: In this valve and apparatus such as a nuclear power plant using the valve, eutectic carbide in alloy having a casting organization basic material portion and the eutectic carbide is formed in plural lumps or plural particles. corrosion/wearing resisting alloy wherein the eutectic carbide is discontinuously distributed is joined to a sliding portion.
    • 要解决的问题:为了提供通过接合耐腐蚀/耐磨合金而具有优异的耐腐蚀/耐腐蚀性和可维护性的阀,其中共晶碳化物通过钎焊不连续地分布到各种装置和阀的滑动部分,以提高火力发电厂的可维护性 和核电站,并提供核电厂工作安全性优良,并拥有一级循环冷却水循环系统。 解决方案:在这种阀和装置如使用阀的核电站中,具有铸造组织基本材料部分的合金中的共晶碳化物和共晶碳化物形成为多个块状或多个颗粒。 其中共晶碳化物不连续分布的耐腐蚀/耐磨合金接合到滑动部分。
    • 10. 发明专利
    • CORROSION CRACKING RESISTANCE IMPROVING METHOD OF NUCLEAR REACTOR PIPING
    • JPH10170693A
    • 1998-06-26
    • JP33333896
    • 1996-12-13
    • HITACHI LTD
    • URAYAMA YOSHINAOKUNIYA JIROANDO MASASHI
    • G21D1/00
    • PROBLEM TO BE SOLVED: To improve corrosion cracking resistance of carbon steel piping, carbon steel welded piping and an apparatus by completely removing cooling water stagnating in the piping after operation of a nuclear reactor is stopped. SOLUTION: Even if drain processing of a coolant is performed after operation is stopped, cooling water stagnates in piping by a part. A method of sending a hot blast into a piping inside part, a method of heating a cooling water stagnating part by a heating coil from a pipe outside surface and a method of spraying a hot blast on the stagnating part from outside of a pipe, exist as a processing method of removing the cooling water. In a hot blast sending method, a hot blast of 200 to 300 deg.C not less than 50 deg.C is sent into at 500cc/sec or more. It is heated to 200 to 300 deg.C not less than 100 deg.C by the heating coil, and at hot blast spraying time, a temperature is set to the same temperature, and wind speed is set not less than 500cc/sec. It is effective when completely evaporated and removed by such heat treatment. Therefore, since a carbon steel apparatus and a carbon steel welded structure having excellent corrosion cracking resistance can be formed in a BWR reactor water environment, safety of a BWR is secured, and the service life of a nuclear power plant can be lengthened.