Method for manufacturing oxidic nuclear fuel bodies
    1.
    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

    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 for the manufacture of oxidic sintered nuclear fuel bodies
    2.
    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

    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 the manufacture of oxide sintered nuclear fuel bodies
    3.
    发明授权
    Method for the manufacture of oxide sintered nuclear fuel bodies 失效
    制造氧化物烧结核燃料体的方法

    公开(公告)号:US4816193A

    公开(公告)日:1989-03-28

    申请号:US99687

    申请日:1987-09-18

    CPC分类号: G21C3/623 Y02E30/38

    摘要: Method for manufacturing sintered oxidic nuclear fuel bodies by molding uranium oxide starting powder, a mixture of uranium oxide and plutonium oxide starting powder or of uranium-plutonium oxide mixed-crystal starting powder to form blanks and by a heat treatment of these blanks with a U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase developed in them to a degree which can be crystallographically detected at a sintering temperature in the range of 1000.degree. to 1400.degree. C. in an oxidizing and subsequently in a reducing gas atmosphere. The starting powder and/or the blanks are preroasted at a roasting temperature below the sintering temperature in a roasting gas atmosphere with oxidizing action and with an oxygen potential in which the U.sub.4 O.sub.9 (U, Pu).sub.4 O.sub.9 crystal phase is developed and cooled down subsequently to a starting temperature below the roasting temperature in an inert or oxidizing cooling-down gas atmosphere. Starting from this starting temperature, the blanks are heated to the sintering temperature in an inert or oxidizing heating gas atmosphere while maintaining the U.sub.4 O.sub.9 or the (U, Pu).sub.4 O.sub.9 crystal phase.

    摘要翻译: 通过模制氧化铀原料粉末,氧化铀和钚氧化物起始粉末或铀 - 钚氧化物混合起始粉末的混合物来形成烧结氧化物核燃料体的方法以形成坯料并且通过用U4O9热处理这些坯料 或(U,Pu)4 O 9结晶相在一定程度上可以在氧化并随后在还原气体气氛中在1000-1400℃范围内的烧结温度下进行晶体学检测。 起始粉末和/或坯料在具有氧化作用的焙烧气体气氛中的焙烧温度下焙烧,并且其中U4O9(U,Pu)4 O9晶相的氧电位被开发并随后冷却 在惰性或氧化冷却气氛中的起始温度低于焙烧温度。 从该起始温度开始,将坯料在惰性或氧化加热气体气氛中加热至烧结温度,同时保持U4O9或(U,Pu)4 O9晶相。

    Supervision and control of continuous casting
    6.
    发明授权
    Supervision and control of continuous casting 失效
    连铸的监督管理

    公开(公告)号:US4066114A

    公开(公告)日:1978-01-03

    申请号:US604796

    申请日:1975-08-14

    IPC分类号: B22D11/16 B22D11/22 B22D11/12

    CPC分类号: B22D11/22

    摘要: The continuous casting of steel is supervised and controlled by measuring total heat flow and the ratio of upper to lower heat flow into the mold and causing these two valves directly or indirectly to be represented in a two dimensional field. The resulting operating point must remain within an empirically predetermined range for safe operation without skin rupture.

    摘要翻译: 钢的连铸是通过测量总的热流量和进入模具的上下热流的比例进行监控和控制,并直接或间接地将这两个阀门表示在二维场中。 所得到的操作点必须保持在经验上预定的范围内,以便在没有皮肤破裂的情况下进行安全操作。

    Method for determining the contents of a fuel rod
    7.
    发明授权
    Method for determining the contents of a fuel rod 失效
    确定燃料棒内容物的方法

    公开(公告)号:US4663112A

    公开(公告)日:1987-05-05

    申请号:US589513

    申请日:1984-03-14

    CPC分类号: G21C17/06 G01N27/72

    摘要: Method for determining the contents of a fuel rod within a testing range extending in the longitudinal direction of the fuel rod, characterized by the features that(a) the position of a test coil concentrically surrounding the fuel rod is changed from the beginning to the end of the testing range, and(b) in the process, the impedance of the test coil is measured as a function of its position,(c) the test coil is fed with an a-c voltage,(d) the frequency of which is so low that the measurement value in the region of a fuel pellet of pure uranium dioxide is clearly distinguished from that which is measured in the region of a doped fuel pellet.

    摘要翻译: 在燃料棒的纵向延伸的测试范围内确定燃料棒的内容物的方法,其特征在于,(a)同心地围绕燃料棒的测试线圈的位置从开始到结束 (b)在该过程中,测试线圈的阻抗作为其位置的函数被测量,(c)测试线圈被馈送交流电压,(d)其频率是如此 低纯度二氧化铀的燃料颗粒区域中的测量值与在掺杂燃料颗粒的区域中测量值的清楚区别。

    Method for producing oxidic sintered nuclear fuel bodies
    8.
    发明授权
    Method for producing oxidic sintered nuclear fuel bodies 失效
    生产氧化烧结核燃料体的方法

    公开(公告)号:US4671904A

    公开(公告)日:1987-06-09

    申请号:US701566

    申请日:1985-02-14

    CPC分类号: G21C3/623 Y02E30/38

    摘要: UO.sub.2 base powder exhibiting any specific surface and crystallite diameter properties is mixed with rare earth (SE) oxide-containing powder, the particles of which exhibit at least in one surface layer, a crystal lattice of the fluorite type, with the stoichiometric composition (SE.sub.0.5, U.sub.0.5) 0.sub.2.00 and/or form it in sintering; and is compacted to form compacts which are sintered in a gas atmosphere with reducing action at 1500.degree. C. to 1750.degree. C. to form high-density sintered bodies.

    摘要翻译: 表现出任何比表面和微晶直径性质的UO2基粉末与含稀土(SE)氧化物的粉末混合,其中颗粒至少在一个表面层中呈现萤石型晶格,具有化学计量组成(SE0 .5,U0.5)02.00和/或在烧结中形成; 并压实成型,在1500〜1750℃的还原作用的气体气氛中烧结,形成高密度烧结体。

    Method for the manufacture of very dense oxidic nuclear fuel bodies
    9.
    发明授权
    Method for the manufacture of very dense oxidic nuclear fuel bodies 失效
    制造非常致密的氧化核燃料体的方法

    公开(公告)号:US4438050A

    公开(公告)日:1984-03-20

    申请号:US190981

    申请日:1980-09-26

    CPC分类号: G21C3/623 Y02E30/38

    摘要: Manufacture of very dense oxidic fuel bodies of UO.sub.2 with rare earth oxides in which pressed blanks are subjected to sintering in an oxidizing atmosphere at relatively low temperature and are sintered in a reducing atmosphere at a higher temperature. This avoids sintering-inhibiting phases and permits very dense bodies with greater content of rare earth oxides to be produced.

    摘要翻译: 用稀土氧化物制造非常致密的氧化物燃料体,其中压坯在氧化性气氛中在较低温度下进行烧结,并在较高温度下还原气氛中烧结。 这避免了烧结抑制阶段,并且允许产生具有更多含量的稀土氧化物的非常致密的体。

    Fuel Pellet for a Nuclear Reactor and Method for Producing Fuel Pellet
    10.
    发明申请
    Fuel Pellet for a Nuclear Reactor and Method for Producing Fuel Pellet 审中-公开
    核反应堆燃料颗粒和生产燃料颗粒的方法

    公开(公告)号:US20090252279A1

    公开(公告)日:2009-10-08

    申请号:US12333723

    申请日:2008-12-12

    IPC分类号: G21C3/00

    CPC分类号: G21C3/00 G21C3/62 Y02E30/38

    摘要: A fuel pellet for a nuclear reactor contains a matrix made of an oxidic nuclear fuel and a metallic phase that is deposited within or between the fuel grains and is preferably aligned in a radial direction relative to the coating surface of the pellet. A method for producing the fuel pellet includes forming slugs containing a precursor of the metallic phase, which has a melting point lying below the sintering temperature and can be transformed into the metallic phase in sintering conditions, in addition to the oxidic nuclear fuel and other optional additives. The slugs are then sintered. The slugs are heated up so quickly that at least one portion of the precursor is liquefied before being completely transformed into the metallic phase.

    摘要翻译: 用于核反应堆的燃料芯片包含由氧化核燃料和金属相制成的基体,其沉积在燃料颗粒内或燃料颗粒之间,并且优选地相对于颗粒的涂覆表面在径向上对准。 一种生产燃料丸的方法包括形成含有金属相的前体的团块,其熔点低于烧结温度,并且可以在烧结条件下转化为金属相,除了氧化核燃料和其它任选的 添加剂。 然后烧结块状物。 这些lug子被如此快速地加热,使得至少一部分前体在完全转变成金属相之前被液化。