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Calculation of dose components in head phantom for boron neutron capture therapy
Ademir X da Silva1, Verginia R Crispim
1Programa de Engenharia Nuclear, Coordenação dos Programas de Pós-Graduação de Engenharia (COPPE), Departamento de Engenharia Nuclear, Universidade Federal do Rio de Janeiro, Ilha do Fundão, 21945-970, Rio de Janeiro, RJ, Brazil. ademir@lmn.con.ufrj.br
Abstract:
Application of neutrons to cancer treatment has been a subject of considerable clinical and research interest since the discovery of the neutron by Chadwick in 1932 (3). Boron neutron capture therapy (BNCT) is a technique of radiation oncology which is used in treating brain cancer (glioblastoma multiform) or melanoma and that consists of preferentially loading a compound containing 10B into the tumor location, followed by the irradiation of the patient with a beam of neutron. Dose distribution for BNCT is mainly based on Monte Carlo simulations. In this work, the absorbed dose spatial distribution resultant from an idealized neutron beam incident upon ahead phantom is investigated using the Monte Carlo N-particles code, MCNP 4B. The phantom model used is based on the geometry of a circular cylinder on which sits an elliptical cylinder capped by half an ellipsoid representing the neck and head, both filled with tissue-equivalent material. The neutron flux and the contribution of individual absorbed dose components, as a function of depths and of radial distance from the beam axis (dose profiles) in phantom model, is presented and discussed. For the studied beam the maximum thermal neutron flux is at a depth of 2 cm and the maximum gamma dose at a depth of 4 cm.
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