Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source

• Published in: Nuclear engineering and technology Vol. 49; no. 4; pp. 787 - 791
• Main Authors: Didi, Abdessamad, Dadouch, Ahmed, Jaï, Otman, Tajmouati, Jaouad, El Bekkouri, Hassane
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.06.2017; Elsevier
• Subjects: Americium–Beryllium Source; Evaluated Nuclear Data File; Monte Carlo N-Particle Transport Code-6; Neutron Activation Analysis; Paraffin; Americium–Beryllium Source; Neutron Activation Analysis; Evaluated Nuclear Data File; Monte Carlo N-Particle Transport Code-6; Paraffin
• ISSN: 1738-5733
• DOI: 10.1016/j.net.2017.02.002

Americium–beryllium (Am-Be; n, γ) is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci), yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.