In recent years, much attention has been dedicated to finding techniques to reduce
exposure doses. This work examines the effectiveness of using serpentine concrete to …

Abstract Americium–beryllium (Am-Be; n, γ) is a neutron emitting source used in various
research fields such as chemistry, physics, geology, archaeology, medicine, and …

Monte Carlo (MCNP-5) simulations of the neutron fluxes were performed to determine the
radial and axial neutron fluxes of the two irradiation sites of the 20Ci 241Am–Be neutron …

Abstract Laboratory measurements and Monte Carlo simulations were conducted to
investigate the feasibility of employing a (reflector/shield) to improve the efficiency of a …

The americium–beryllium neutron irradiation facility at the National Nuclear Research
Institute (NNRI), Ghana, was re-designed with four 20 Ci sources using Monte Carlo N …

Using irradiated doped-silica preforms from which fibres for thermoluminescence dosimetry
applications can be fabricated we have carried out a range of luminescence studies, the TL …

Evaluation of the flux in various irradiation channels and the absorbed dose rate of radiation
by operators 3cm from the surface of the concrete surrounding the vessel of the 241Am–Be …

Abstract The Nuclear Engineering Department of the Military Institute of Engineering (SE/7-
IME) is designing and simulation a neutron irradiator with 1 Ci of 241 Am-9 Be source. The …

Neutron activation analysis (NAA) is a sensitive nondestructive method for determining the
elemental composition of a simple. Nuclear reactors are frequently used for NAA because of …

Monte Carlo studies aimed at designing a modular 241Am-Be neutron irradiator for testing
neutron detectors and personal dosimeters and processing large volume samples are …