Method and apparatus for detecting neutrons
    1.
    发明授权
    Method and apparatus for detecting neutrons 失效
    用于检测中子的方法和装置

    公开(公告)号:US5680423A

    公开(公告)日:1997-10-21

    申请号:US410169

    申请日:1995-03-24

    IPC分类号: G01T3/06

    CPC分类号: G01T3/06

    摘要: The instant invention is a method for making and using an apparatus for detecting neutrons. Scintillating optical fibers are fabricated by melting SiO.sub.2 with a thermal neutron capturing substance and a scintillating material in a reducing atmosphere. The melt is then drawn into fibers in an anoxic atmosphere. The fibers may then be coated and used directly in a neutron detection apparatus, or assembled into a geometrical array in a second, hydrogen-rich, scintillating material such as a polymer. Photons generated by interaction with thermal neutrons are trapped within the coated fibers and are directed to photoelectric converters. A measurable electronic signal is generated for each thermal neutron interaction within the fiber. These electronic signals are then manipulated, stored, and interpreted by normal methods to infer the quality and quantity of incident radiation. When the fibers are arranged in an array within a second scintillating material, photons generated by kinetic neutrons interacting with the second scintillating material and photons generated by thermal neutron capture within the fiber can both be directed to photoelectric converters. These electronic signals are then manipulated, stored, and interpreted by normal methods to infer the quality and quantity of incident radiation.

    摘要翻译: 本发明是用于制造和使用用于检测中子的装置的方法。 闪烁光纤通过在还原气氛中用热中子捕获物质和闪烁材料熔化SiO 2来制造。 然后将熔体在缺氧气氛中吸入纤维中。 然后可以将纤维涂覆并直接用于中子检测装置,或者在第二富氢闪烁材料如聚合物中组装成几何阵列。 通过与热中子的相互作用产生的光子被捕获在涂覆的光纤内并被引导到光电转换器。 为光纤内的每个热中子相互作用产生可测量的电子信号。 然后通过常规方法对这些电子信号进行操作,存储和解释,以推断入射辐射的质量和数量。 当纤维以阵列排列在第二闪烁材料内时,通过与第二闪烁材料相互作用的动能中子产生的光子和光纤内的热中子俘获产生的光子都可以被引导到光电转换器。 然后通过常规方法对这些电子信号进行操作,存储和解释,以推断入射辐射的质量和数量。

    Method for homogenizing mixed oxide nuclear fuels
    2.
    发明授权
    Method for homogenizing mixed oxide nuclear fuels 失效
    混合氧化物核燃料均质化方法

    公开(公告)号:US4261934A

    公开(公告)日:1981-04-14

    申请号:US965144

    申请日:1978-11-30

    CPC分类号: C04B35/51 G21C3/623 Y02E30/38

    摘要: A method for homogenizing plutonia particles in mixed oxide nuclear reactor fuels. The method includes the step of blending urania particles and plutonia particles together and pressing the mixture into a pellet. The pellet is thereafter sintered in a reducing atmosphere with hydrogen present so that pores are formed in the pellet. The plutonia particles are thereby transformed into spherical shells of dense PuO.sub.2-x that surround each pore and which homogenizes the fuel.

    摘要翻译: 在混合氧化物核反应堆燃料中均质化plutonia颗粒的方法。 该方法包括将尿素颗粒和plutonia颗粒混合在一起并将混合物压制成颗粒的步骤。 然后将该颗粒在还原气氛中用存在的氢气进行烧结,使得在颗粒中形成孔。 因此,plutonia颗粒被转化成围绕每个孔并使燃料均化的致密PuO 2-x的球形壳。