Nuclear and radiological characterization of a 226Ra-Be neutron irradiator at INFISA-UNMSM, Peru, using Monte Carlo simulation with the OpenMC code

IF 2.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2026-06-01 Epub Date: 2026-02-10 DOI:10.1016/j.net.2026.104158

P. Tataje , Abdessamad Didi , A. Arroyo , S. Daza

引用次数: 0

Abstract

A neutron irradiator consisting of a²²⁶Ra-Be source with a 3 mCi activity of radium, used for the early teaching of neutron activation experiments, belonging to the INFISA-UNMSM, was characterized using the relatively new open-source framework OpenMC. The ²²⁶Ra-Be source is located inside a hermetically sealed nickel-soldered cylinder filled with activated carbon. This cylinder, in turn, is inside a larger cylinder filled with paraffin wax, with seven irradiation channels. These channels were characterized for axial and radial neutron flux, prompt gamma flux, and dose equivalent rate (H∗₍₁₀₎) both inside the irradiation channels and on the exterior of the cylinder.

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秘鲁INFISA-UNMSM的226Ra-Be中子辐照器的核和放射特性，使用蒙特卡罗模拟和OpenMC代码

利用相对较新的开放源代码框架OpenMC对用于中子活化实验早期教学的中子辐照体进行了表征，该中子辐照体由镭活度为3mci的226ra - be源组成。226Ra-Be源位于一个密封的镍焊气缸内，气缸内填充活性炭。这个圆柱体，反过来，是在一个更大的圆柱体充满石蜡，有七个辐照通道。这些通道的特征是轴向和径向中子通量，提示伽马通量和剂量等效率（H *(10)）在辐照通道内和柱体的外部。

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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来源期刊

Nuclear Engineering and Technology 工程技术-核科学技术

CiteScore

4.80

自引率

7.40%

发文量

431

审稿时长

3.5 months

期刊介绍： Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development