Determination of 54Mn and 59Fe Specific Activities in Iron Plates Activation Detectors

Lyuben Dobrev, Mladen Mitev, Dobromir Dimitrov, T. Nonova, Z. Zahariev, Desislava Dimitrova, Srgjan Krstevski, Bozhidar Slavchev
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Abstract

In reactor dosimetry it is well known that the empirical determination of the neutron flux is performed by determining the isotope 54Mn generated in a (n, γ) nuclear reaction. This study presents a procedure for the simultaneous determination of the radioisotopes 54Mn and 59Fe, developed to obtain more complete information about the process. The basis of the method is the irradiation of iron-plate detectors with a neutron flux generated in a VVER-type nuclear reactor and subsequent gamma spectrometric analysis of the samples to determine the two radionuclides obtained in two simultaneous (n,x) and (n, γ) nuclear reactions. A very important stage of the assay is the preliminary radiochemical treatment of the samples involving the removal of oxides and corrosion products and the dissolution of the plates in strong mineral acids. The results show that our approach of simultaneous determination of 54Mn and 59Fe significantly improves the time of analyses, reduces the radiation dose, and increases the accuracy and efficiency of neutron fluence determination. The procedures are relatively easy to perform and are suitable for application in routine studies.
铁板活化探测器中 54Mn 和 59Fe 比活度的测定
在反应堆剂量测定中,众所周知,中子通量的经验测定是通过测定在(n,γ)核反应中产生的同位素 54Mn 来进行的。本研究提出了一种同时测定放射性同位素 54Mn 和 59Fe 的程序,以获得有关这一过程的更完整信息。该方法的基础是用在 VVER 型核反应堆中产生的中子通量辐照铁板探测器,然后对样品进行伽马能谱分析,以确定在两个同时发生的(n,x)和(n,γ)核反应中获得的两种放射性核素。检测的一个非常重要的阶段是对样品进行初步的放射化学处理,包括去除氧化物和腐蚀产物,以及将平板溶解在强矿物酸中。结果表明,我们同时测定 54Mn 和 59Fe 的方法大大缩短了分析时间,减少了辐射剂量,提高了中子通量测定的准确性和效率。该方法操作相对简单,适合在常规研究中应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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