Monte Carlo simulation of thermal neutron flux of americium–beryllium source used in neutron activation analysis

• Published in: Moscow University physics bulletin Vol. 72; no. 5; pp. 460 - 464
• Main Authors: Didi, Abdessamad, Dadouch, Ahmed, Bencheikh, Mohamed, Jai, Otman
• Format: Journal Article
• Language: English
• Published: Moscow Pleiades Publishing 01.09.2017; Springer Nature B.V
• Subjects: Activation analysis; Americium; Barriers; Beryllium; Computer simulation; Heat transmission; Mathematical and Computational Physics; Monte Carlo simulation; Neutron activation analysis; Neutron flux; Neutrons; Nuclear reactors; Particle accelerators; Physics; Physics and Astronomy; Physics of Nuclei and Elementary Particles; Radioisotopes; Theoretical; MCNP-6; paraffin; ENDF; Am–Be source; NAA; PGNAA
• ISSN: 0027-1349; 1934-8460
• DOI: 10.3103/S0027134917050022

The neutron activation analysis is a method of exclusively elemental analysis. Its implementation of irradiates the sample which can be analyzed by a high neutron flux, this method is widely used in developed countries with nuclear reactors or accelerators of particle. The purpose of this study is to develop a prototype to increase the neutron flux such as americium–beryllium and have the opportunity to produce radioisotopes. Americium–beryllium is a mobile source of neutron activity of 20 curie, and gives a thermal neutron flux of (1.8 ± 0.0007) × 10 6 n/cm 2 s when using water as moderator, when using the paraffin, the thermal neutron flux increases to (2.2 ± 0.0008) × 10 6 n/cm 2 s, in the case of adding two solid beryllium barriers, the distance between them is 24 cm, parallel and symmetrical about the source, the thermal flux is increased to (2.5 ± 0.0008) × 10 6 n/cm 2 s and in the case of multi-source (6 sources), with-out barriers, increases to (1.17 ± 0.0008) × 10 7 n/cm 2 s with a rate of increase equal to 4.3 and with the both barriers flux increased to (1.37 ± 0.0008) × 10 7 n/cm 2 s.