Monte Carlo simulation of thermal neutron flux of Americium Beryllium source is used in neutron activation analysis
A. Didi, A. Dadouch, M. N. Bencheikh, J. Tajmouati, O. Jai
Вестн. Моск. ун-та. Сер. 3. Физ. Астрон. 2017. № 5.
Abstract: 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) × 106 n/cm²s when using water as moderator, when using the paraffin, the thermal neutron flux increases to (2.2 ± 0.0008) × 106 n/cm²s, 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) × 106 n/cm²s and in the case of multi-source (5 sources), with-out barriers, increases to (1,09 ± 0.0008) × 107 n/cm²s with a rate of increase equal to 4,3 and with the both barriers flux increased to (1,22 ± 0,0008) × 107 n/cm²s.
Keywords: MCNP-6, ANN, Am-Be source, Paraffin , ENDF, PGNAA