反应堆中子环境中93mNb活度测量中182Ta和94Nb贡献的快速减去方法

Jianguo Qin , Yaping Zhang , Chuanxin Zhu , Caifeng Lai , Kai Li , Tonghua Zhu , Li An , Xinxin Lu , Yunfeng Mu
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引用次数: 0

摘要

铌是反应堆外使用的最重要的中子剂量计之一。由于182Ta和94Nb放射性核素的荧光效应,利用Nb的中子非弹性散射产生的93mNb的活度的快速求出是一个问题。为了解决这一问题,提出了一种基于蒙特卡罗模拟的快速估计方法。考虑了铌样品中放射性核素的γ射线、β射线和内部转换电子引起的荧光效应的所有贡献。结果表明,计算值与实验值的偏差小于8.0%。结果表明,该方法仅基于一次实验测量,就可以快速减去荧光效应对铌样品活度测量的贡献。
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A method for quickly subtracting the contributions from 182Ta and 94Nb in activity measurement of 93mNb in reactor neutron environment

Niobium is one of the most important neutron dosimeters used outside of the reactor. Owing to the fluorescence effects of 182Ta and 94Nb radionuclides, it is a problem to quickly obtain the activity of 93mNb which produced by the neutron inelastic scattering of Nb. To solve this problem, a fast estimating method based on the Monte Carlo simulation is proposed. All the contributions from fluorescence effects that induced by gamma-rays, beta-rays and internal conversion electrons of the radionuclides in the niobium sample were considered. The comparison results demonstrated that the deviation is less than 8.0% between the calculated and the experimental activities. It shows that the contribution of radionuclide by fluorescence effects in activity measurement of the niobium sample can be subtracted quickly using this method, based just once experimental measurement.

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