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    • 2. 发明授权
    • Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact with fuel rods and enlarged elastic range
    • 具有栅格弹簧的核反应堆燃料组件的间隔栅格保持与燃料棒的保形接触和扩大的弹性范围
    • US06707872B2
    • 2004-03-16
    • US10010526
    • 2001-12-07
    • Kyung Ho YoonHeung Seok KangHyung Kyu KimKee Nam SongYoun Ho JungTae Hyun ChunDong Seok OhWang Kee InGyung Jin Park
    • Kyung Ho YoonHeung Seok KangHyung Kyu KimKee Nam SongYoun Ho JungTae Hyun ChunDong Seok OhWang Kee InGyung Jin Park
    • G21C334
    • G21C3/3563G21Y2002/303G21Y2004/301Y02E30/40
    • A spacer grid used for placing and supporting fuel rods in nuclear reactor fuel assemblies is disclosed. The spacer grid of this invention has a plurality of grid springs designed to have an optimal shape of their vertical support parts, thus reducing fretting wear of the fuel rods caused by contact of the fuel rods with the grid springs. The grid spring has a vertical support part and a fuel rod support part. The vertical support part includes upper and lower base parts extending downward and upward from the central portions of the top and bottom edges of an opening formed at the central portion of a unit strip, and two bridge parts branched from the upper base part and extending symmetrically downward until they are united at the lower base part. The fuel rod support part includes a conformal support part brought into surface contact with the external surface of a fuel rod. Two transverse connection parts extend outward from the opposite outside edges of the conformal support part while being specifically bent, and are integrated with the central portions of the inside edges of the two bridge parts into a single structure, thus connecting the fuel rod support part to the vertical support part.
    • 公开了一种用于将燃料棒放置和支撑在核反应堆燃料组件中的间隔栅格。 本发明的间隔栅格具有多个格栅弹簧,其被设计成具有其垂直支撑部分的最佳形状,从而减少由燃料棒与格栅弹簧的接触引起的燃料棒的微动磨损。 栅格弹簧具有垂直支撑部分和燃料棒支撑部分。 垂直支撑部分包括从形成在单元条的中心部分的开口的顶部和底部边缘的中心部分向下和向上延伸的上部和下部基部,以及从上部基部分支并且对称延伸的两个桥接部分 向下,直到它们结合在下基部。 燃料棒支撑部分包括与燃料棒的外表面接触的共形支撑部分。 两个横向连接部分从保形支撑部分的相对的外边缘向外延伸,同时被特别弯曲,并且与两个桥接部分的内边缘的中心部分成一体,从而将燃料棒支撑部分连接到 垂直支撑部分。
    • 7. 发明授权
    • Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube
    • 锆合金具有优异的耐燃性和核燃料包层管的机械性能
    • US06811746B2
    • 2004-11-02
    • US10040743
    • 2001-11-01
    • Yong Hwan JeongJong Hyuk BaekByoung Kwon ChoiMyung Ho LeeSang Yoon ParkCheol NamYoun Ho Jung
    • Yong Hwan JeongJong Hyuk BaekByoung Kwon ChoiMyung Ho LeeSang Yoon ParkCheol NamYoun Ho Jung
    • C22C1600
    • C22F1/186C22C16/00G21C3/07Y02E30/40
    • The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bSn-cFe-dCr-eCu (a=0.05-0.4 wt %, b=0.3-0.7 wt %, c=0.1-0.4 wt %, d=0-0.2 wt % and e=0.01-0.2 wt %, provided that Nb+Sn=0.35-1.0 wt %), and to a method for preparing a zirconium alloy nuclear fuel cladding tube, comprising melting a metal mixture comprising of the zirconium and alloying elements to obtain ingot, forging the ingot at &bgr; phase range, &bgr;-quenching the forged ingot at 1015-1075° C., hot-working the quenched ingot at 600-650° C., cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing and final vacuum annealing the worked ingot at 460-540° C., which can be applied to the core components in a light water and a heavy water atomic reactor type nuclear power plant.
    • 本发明涉及具有优异的耐腐蚀性和机械性能的锆合金以及通过锆合金制备核燃料包层管的方法。 更具体地,本发明涉及包含Zr-aNb-bSn-cFe-dCr-eCu(a = 0.05-0.4重量%,b = 0.3-0.7重量%,c = 0.1-0.4重量%,d = 0-0.2重量%,e = 0.01-0.2重量%,条件是Nb + Sn = 0.35-1.0重量%),以及制备锆合金核燃料包层管的方法,包括熔融金属混合物, 锆和合金元素以获得锭,在β相范围锻造锭,在1015-1075℃下对锻造锭进行β淬火,在600-650℃下热处理淬火锭,冷热处理, 在三到五道次的铸锭中进行中间真空退火和最终真空退火处理的锭在460-540℃,可以应用于轻水和重水原子反应堆型核电站的核心部件。