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首页> 外文会议>International Conference on Advances in Destructive and Non-Destructive Analysis for Environmental Monitoring and Nuclear Forensics; 20021021-20021023; Karlsruhe; DE >DETERMINATION OF URANIUM CONTENT OF SAMPLES IN VARIOUS GEOMETRIES BY GAMMA RAY SPECTROMETRY
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DETERMINATION OF URANIUM CONTENT OF SAMPLES IN VARIOUS GEOMETRIES BY GAMMA RAY SPECTROMETRY

机译：γ射线光谱法测定各种几何样品中的铀含量。

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摘要

There are certain limitations to the usage of standard source methods for efficiency calibration of gamma ray spectrometers measuring in extended geometry. These limitations arise from the diversity of forms and dimensions of the objects that are to be measured during uranium fuel fabrication activities. One of the steps in the fuel fabrication cycle is radioactive waste conditioning. The Institute for Nuclear Research (ICN) operates a radioactive waste management facility both for its own purposes and for external services. Conditioning of liquid and solid wastes for interim storage is also done at the waste management facility. Located on the same site as the Institute is a radioactive fuel factory that produces natural uranium based fuel for the Cernavoda nuclear power plant. Some of the radioactive wastes processed at ICN's treatment facility originate from fuel factory activities and contain natural uranium. A large part of this uranium is recovered and, therefore, returned to the fuel factory, but there is a certain amount of uranium that has to be eliminated as radioactive waste. During waste conditioning operations there are certain stages when radioactive measurement of storage drums is required. We have developed gamma ray spectrometry equipment, using a portable MCA Canberra Inspector, an HPGe detector and an ICN manufactured collimator, which we are using as a semi-empirical means of calibrating the gamma ray spectrometer for such measurements.
机译：使用标准源方法进行扩展几何形状中的伽马射线光谱仪效率校准存在一定的局限性。这些限制是由于铀燃料制造活动中要测量的物体的形式和尺寸的多样性而引起的。燃料制造循环中的步骤之一是放射性废料的调理。核研究所（ICN）既出于自身目的又为外部服务运营着放射性废物管理设施。还可以在废物管理设施中对液体和固体废物进行临时储存的调节。与研究所位于同一地点的是一家放射性燃料工厂，该工厂为切尔纳沃达核电站生产天然铀基燃料。在ICN的处理设施中处理的一些放射性废物来自燃料工厂的活动，并含有天然铀。该铀的大部分被回收并因此返回燃料厂，但仍有一定量的铀必须作为放射性废物清除。在废物处理操作期间，需要进行某些阶段的放射性测量储气罐。我们使用便携式MCA堪培拉检查仪，HPGe检测器和ICN制造的准直仪开发了伽马射线光谱仪，这些仪器被用作校准此类测量的伽马射线光谱仪的半经验方法。

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