Designing a Transportable Neutron Radiography System

Authors

  • Roppon Picha Thailand Institute of Nuclear Technology (TINT), 16 Vibhavadi Rangsit Rd, Chatuchak, Bangkok 10900, Thailand.
  • Narut Simaroj Srinakharinwirot University, 114 Sukhumvit 23, Wattana, Bangkok 10110, Thailand.
  • Viwat Sangphet King Mongut’s Institute of Technology Ladkrabang, Ladkrabang, Bangkok 10520, Thailand.

Keywords:

neutron, radiography, simulation, detector, radiation, Monte Carlo

Abstract

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.

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Published

2008-12-31

How to Cite

Roppon Picha, Narut Simaroj, and Viwat Sangphet. 2008. “Designing a Transportable Neutron Radiography System”. Agriculture and Natural Resources 42 (5). Bangkok, Thailand:305-10. https://li01.tci-thaijo.org/index.php/anres/article/view/244612.

Issue

Vol. 42 No. 5 (2008): January-December

Section

Research Article

License

online 2452-316X print 2468-1458/Copyright © 2022. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/),
production and hosting by Kasetsart University of Research and Development Institute on behalf of Kasetsart University.