Silva F S, Martins M M, Conti C C, Leite S P, Fonseca E S, Patrão K C S, Pereira W W
Instituto de Radioproteção e Dosimetria, Av. Salvador Allende, RJ, Brazil.
Fundação Técnico-Educacional Souza Marques, Av. Ernani Cardoso 335, RJ, Brazil.
Radiat Prot Dosimetry. 2018 Aug 1;180(1-4):42-45. doi: 10.1093/rpd/ncy011.
This study describes the use of a neutron irradiator system based on a plutonium-beryllium neutron source for MnSO4 solution activation for use to determine the MSB system efficiency. Computational simulations using Monte Carlo code were performed to establish the main characteristics of the irradiator system. Among the simulated geometries and volumes, semi-cylindrical shape with 84.5 cm3 of MnSO4 solution yielded the best option to be built. Activity measurements were performed with a high-pure germanium detector to validate the new irradiation system. Results showed an average efficiency and uncertainty of the experimental standard deviation of the mean: 5.742 × 10-4 ± 0.036 × 10-4 (coverage factor k = 1), for MSB system. Efficiency value obtained shows good correlation to other published methods (i.e. a relative difference of 0.07%). This alternative metrological method demonstrated the utility of neutron sources for the irradiation of solutions in metrology laboratories providing a cost-efficient alternative to nuclear reactors or particle accelerators.
本研究描述了一种基于钚铍中子源的中子辐照系统用于激活硫酸锰溶液以确定MSB系统效率的情况。使用蒙特卡罗代码进行了计算模拟，以确定辐照系统的主要特性。在模拟的几何形状和体积中，装有84.5立方厘米硫酸锰溶液的半圆柱形是最佳的构建选择。使用高纯锗探测器进行了活度测量，以验证新的辐照系统。结果显示，MSB系统的平均效率和平均实验标准偏差的不确定度为：5.742×10⁻⁴±0.036×10⁻⁴（覆盖因子k = 1）。获得的效率值与其他已发表的方法具有良好的相关性（即相对差异为0.07%）。这种替代计量方法证明了中子源在计量实验室中用于溶液辐照的实用性，为核反应堆或粒子加速器提供了一种经济高效的替代方案。
