عنوان مقاله [English]
نویسنده [English]چکیده [English]
Neutrons are used for medical, shielding and material research. The neutron has a greater linear energy transfer, and is considered a perilous radiation in comparison with gamma-rays. In recent years the use of (α, n) neutron sources are increased because of their high neutron yield. 241Am-Be is one of them that is widely used in many research centers and universities as a calibration source of neutron radiation. To calculate dose rates of Gamma and neutron from 241Am-Be source, measure its intensity, is one of the essential and important tasks. Strength of a 241Am-Be Neutron Source determined by the BF3 detector with the spatial integration method and error of the experiment, with applied corrections by Dysprosium and Gold foils has been reduced to less than 10.30%. Also, the 241Am-Be neutron source, BF3 detector and water tank were simulated with a Monte Carlo method and there is a good agreement between simulation and experimental results.