Facure A, Da Silva A X, Falcão R C
Comissão Nacional de Energia Nuclear, R. Gal. Severiano 90, sala 405, Rio de Janeiro, RJ 22294-900, Brazil.
Radiat Prot Dosimetry. 2007;123(1):56-61. doi: 10.1093/rpd/ncl080. Epub 2006 Jun 30.
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.
在这项工作中,通过蒙特卡罗模拟研究了放射治疗室中散射光中子注量和热光中子注量的行为。使用MCNP代码研究了这些中子注量对房间设计、房间面积以及放置在房间墙壁上的中子慢化材料的影响。研究结果表明,模拟结果与经验近似值之间的一致性较差,这表明文献中发现的公式可能会低估放射治疗室内的中子通量。