Radiation Protection Dosimetry Advance Access published online on June 30, 2006
Radiation Protection Dosimetry, doi:10.1093/rpd/ncl080
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SCIENTIFIC AND TECHNICAL PAPER
1 Comissão Nacional de Energia Nuclear, R. Gal. Severiano 90, sala 405, Rio de Janeiro, RJ 22294-900, Brazil
* To whom correspondence should be addressed.
In this work, the behaviour of scattered and thermal photoneutron fluences in a radiotherapy treatment room was investigated by means of Monte Carlo simulation. The MCNP code was used to study the dependence of these neutron fluences on room design, room area and the effect of neutron moderator materials placed on the room walls. The results of the investigation showed a poor agreement between the simulations and empirical approximations, suggesting that the formulae found in the literature can underestimate the neutron flux inside a radiotherapy room.
Received November 1, 2005
Revised March 26, 2006
Accepted May 29, 2006
MONTE CARLO SIMULATION OF SCATTERED AND THERMAL PHOTONEUTRON FLUENCES INSIDE A RADIOTHERAPY ROOM
A. Facure 1 *,
A. X. Da Silva 2,
and
R. C. Falcão 1
2 [PEN/COPPE--DNC/EE]CT/UFRJ, Ilha do Fundão, PO Box 68509, Rio de Janeiro, RJ 21945-970, Brazil
A. Facure, E-mail: afacure{at}cnen.gov.br
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