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    Method for repairing an oxide superconducting connecting line
    2.
    发明授权
    Method for repairing an oxide superconducting connecting line 失效
    氧化物超导连接线修复方法

    公开(公告)号：US5221663A

    公开(公告)日：1993-06-22

    申请号：US731379

    申请日：1991-07-16

    申请人： Helmut Assmann

    发明人： Helmut Assmann

    IPC分类号： C01B13/14 ,  C01G1/00 ,  C23C8/16 ,  H01B12/12 ,  H01B13/00 ,  H01L39/14 ,  H01L39/24

    CPC分类号： H01B12/12 ,  H01L39/143 ,  H01L39/248 ,  Y02E40/641 ,  Y10S505/701 ,  Y10S505/703 ,  Y10S505/736

    摘要： A method for producing an oxide superconducting connecting line includes initially coating a line with at least one layer of a crystalline or amorphous metal alloy forming a superconductive oxide. The line is subsequently heated to a temperature below the melting temperature of the oxide. A gas containing oxygen is simultaneously brought into contact with the accessible surface forming an oxide film which is superconductive upon cooling. When the oxide film is damaged at a certain location, the still-undamaged layer is exposed to the oxygen-containing gas and the line is heated at the damaged location. A superconducting film is again formed. A combination superconducting connecting line and an apparatus for producing the superconducting connecting line is also disclosed.

    摘要翻译： 一种生产氧化物超导连接线的方法包括：首先用至少一层形成超导氧化物的结晶或无定形金属合金涂覆线。 随后将该线加热到低于氧化物的熔融温度的温度。 含氧的气体同时与可触及的表面接触，形成在冷却时超导的氧化膜。 当氧化膜在一定位置被损坏时，仍然没有损伤的层暴露于含氧气体，并且在损坏的位置加热管线。 再次形成超导膜。 还公开了一种组合超导连接线和用于制造超导连接线的装置。

    Method for the manufacture of oxidic sintered nuclear fuel bodies
    4.
    发明授权
    Method for the manufacture of oxidic sintered nuclear fuel bodies 失效
    制造氧化烧结核燃料体的方法

    公开(公告)号：US4578229A

    公开(公告)日：1986-03-25

    申请号：US436303

    申请日：1982-10-25

    申请人： Helmut Assmann ,  Gerhard Dichtjar ,  Wolfgang Dorr ,  Georg Maier ,  Viktor Mathieu ,  Martin Peehs

    发明人： Helmut Assmann ,  Gerhard Dichtjar ,  Wolfgang Dorr ,  Georg Maier ,  Viktor Mathieu ,  Martin Peehs

    IPC分类号： G21C3/62 ,  G21C21/00

    CPC分类号： G21C3/623 ,  Y02E30/38

    摘要： Method for the manufacture of oxidic nuclear fuel bodies by a heat treatment of blanks obtained from UO.sub.2 starting power or a mixture of UO.sub.2 and PuO.sub.2 starting powder at a treatment temperature in the range of 1000.degree. C. to 1400.degree. initially in a gas atmosphere with oxidizing action and subsequently in a gas atmosphere with reducing action. The oxygen potential of the gas atmosphere with oxidizing action is kept in a range in which a crystallographically demonstrable U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase is generated in the blanks during the heating to the treatment temperature in this gas atmosphere with oxidizing action.

    摘要翻译： 在氧气核燃料体的热处理中，由UO2起动力获得的坯料或者在1000℃至1400℃的处理温度下的UO2和PuO2起始粉末的混合物在气体气氛中进行热处理的方法， 氧化作用，随后在具有还原作用的气体气氛中。 具有氧化作用的气体气氛的氧气被保持在在氧化作用的气体气氛中加热至处理温度期间在坯料中产生结晶学上可见的U4O9或（U，Pu）4O9结晶相的范围内。

    Method for manufacturing oxidic nuclear fuel bodies
    5.
    发明授权
    Method for manufacturing oxidic nuclear fuel bodies 失效
    制造氧化物核燃料体的方法

    公开(公告)号：US4348339A

    公开(公告)日：1982-09-07

    申请号：US104973

    申请日：1979-12-18

    申请人： Helmut Assmann ,  Egbert Brandau ,  Wolfgang Dorr ,  Viktor Mathieu ,  Gerhard Dichtjar

    发明人： Helmut Assmann ,  Egbert Brandau ,  Wolfgang Dorr ,  Viktor Mathieu ,  Gerhard Dichtjar

    IPC分类号： C04B35/622 ,  G21C3/00 ,  G21C3/62 ,  G21C21/00 ,  G21C21/02

    CPC分类号： G21C3/623 ,  Y02E30/38

    摘要： Manufacture of oxidic nuclear fuel bodies with oxygen-to-metal ratio of 2.0.+-.0.02 at relatively low sintering temperature in range of 1000.degree.-1400.degree. C. Nuclear fuel powder with an arbitrary oxygen-to-metal ratio is mixed with a grain-growth promoting additive (U.sub.3 O.sub.8) and pressed into blanks. The blanks are subjected to a two-stage operation in a furnace at 1000.degree.-1400.degree. C. - an oxidative-sintering stage in a carbon dioxide atmosphere and a reducing stage in a hydrogen containing atmosphere.

    摘要翻译： 在比较低的烧结温度下在1000°-1400℃的范围内，氧 - 金属比为2.0 +/- 0.02的氧化核燃料体的制造。具有任意氧 - 金属比的核燃料粉末与 颗粒生长促进添加剂（U3O8）并压成坯料。 坯料在1000-140℃的炉中进行两阶段操作 - 在二氧化碳气氛中的氧化烧结阶段和在含氢气氛中的还原阶段。

    Method and equipment for detecting deflective nuclear fuel rods
    6.
    发明授权
    Method and equipment for detecting deflective nuclear fuel rods 失效
    用于检测偏转核燃料棒的方法和设备

    公开(公告)号：US3945245A

    公开(公告)日：1976-03-23

    申请号：US452254

    申请日：1974-03-18

    申请人： Heinz Stehle ,  Helmut Assmann ,  Peter Wahode ,  Walter Janson

    发明人： Heinz Stehle ,  Helmut Assmann ,  Peter Wahode ,  Walter Janson

    IPC分类号： G21C17/07 ,  G01N29/00 ,  G01M3/04

    CPC分类号： G21C17/07

    摘要： Nuclear fuel rod ends of water-cooled reactor fuel rods, are heated in the region of the fission gas plenums and/or in the region of the upper or lower ends of the fuel columns. The moisture present in the case of damage to the fuel rods' casings, evaporates and is partly condensed at the end caps. In the case of a fuel rod completely filled with water, steam bubbles are generated. Both indications of casing leakage or damage are ascertained by ultrasonic reflection measurements and/or measurement of a temperature-vs-time curve, obtained at the end cap.

    摘要翻译： 水冷反应堆燃料棒的核燃料棒端部在裂变气体增压室的区域和/或燃料柱的上端或下端区域被加热。 在燃料棒壳体损坏的情况下存在的水分蒸发并在端盖处部分冷凝。 在燃料棒完全充满水的情况下，产生蒸气泡。 通过超声波反射测量和/或在端盖获得的温度 - 时间 - 曲线的测量来确定套管泄漏或损坏的两个迹象。