Designing a Transportable Neutron Radiography System

บทคัดย่อ

Aspects of a neutron radiography setup, including the energy and geometry of the neutron source, the material choices and geometry of the moderation system, and the geometry of the imaging section and of the shielding system, via Monte Carlo methods are described. We evaluated the practicality of a transportable neutron radiography system. Calculations of neutron fluxes and energy distributions due to an americium-beryllium neutron source were performed using MCNP (Monte Carlo N-Particle) software package. The result shows that the safe source activity level is in the order of micro-Ci. This demonstrates the challenges in constructing a practical, efficient, and safe radiography system.