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首页> 外文期刊>Review of Scientific Instruments >Method for Obtaining a Component of Approximately Collimated Fast Neutrons in a Reactor
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Method for Obtaining a Component of Approximately Collimated Fast Neutrons in a Reactor

机译:在反应堆中获得准直快中子成分的方法

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摘要

By locating a uranium slug in the reflector of a graphite reactor, at the edge of the loading, an approximately collimated fast neutron flux is obtained which is at least twice the random background fast flux. The relative intensity of the collimated flux is determined by the separation between slug and sample. Close to the slug the directed flux is high and the collimation poor, and by increasing the separation, the collimation is increased but at the expense of intensity. The fast flux in the region where samples are located was determined using the U238 fast fission reaction. The spatial dependence of the directed flux can be approximated by an inverse square expression.
机译:通过将铀弹头放置在石墨反应堆的反射器中,在装料的边缘,可获得近似准直的快中子通量,该通量至少是随机本底快通量的两倍。准直通量的相对强度由段塞和样品之间的距离确定。靠近弹头,定向通量高而准直性差,并且通过增加间隔,准直度增加了,但是以强度为代价。使用U238快速裂变反应确定样品所在区域的快速通量。定向通量的空间依赖性可以通过平方反比来近似。

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  • 来源
    《Review of Scientific Instruments》 |1960年第8期|共2页
  • 作者

    Levy Paul W.;

  • 作者单位

    Brookhaven National Laboratory, Upton, Long Island, New York;

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  • 原文格式 PDF
  • 正文语种 eng
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