Neutrons along the labyrinth of high energy medical accelerators: Effect of wall materials


Keywords:
Radiation Shielding Medical Accelerator Neutron streaming Monte Carlo simulations
M. Fakinou
I. E. Stamatelatos
J. Kalef-Ezra
Abstract

Neutron streaming along the labyrinth of a generic bunker of an 18MV medical accelerator was evaluated. Monte Carlo simulations using MCNP code were performed to calculate neutron ambient dose equivalent along the labyrinth. The effect of plain, borated and barites concrete wall material, as well as borated concrete and plywood (Celotex), as neutron absorbing wall liners, was examined. The results of the study suggest that plywood can provide a cost effective material to attenuate neutron streaming along the labyrinth.

Article Details
  • Section
  • Poster contributions
References
E. Carinou, V. Kamenopoulou, Evaluation of neutron dose in the maze of medical accelerators, Medical Physics 26 (2006) 2520–2525.
X-5 Monte Carlo Team, MCNP Version 5, LA-UR-03-1987, Los Alamos (2003).
IAEA, Compendium of Neutron Spectra for Radiation Protection, TRS No. 318, Vienna (1990).
ICRP Publication 103, The 2007 Recommendations of the International Commission on Radiological Protection, Ann. ICRP 37 (2-4) (2007).