RESUMO
The thermal neutron flux in a fast neutron therapy treatment unit is measured by a small ionization chamber coated inside with boron (10B). These measurements are compared with calculations of the thermal neutron flux made by a pencil beam algorithm, which can be used as a first approximation for treatment therapy planning. The additional dose for boron neutron capture therapy (BNCT) as a boost in a 14 MeV neutron generator is calculated from the measured thermal neutron flux.
Assuntos
Terapia por Captura de Nêutron de Boro , Nêutrons Rápidos , Neoplasias/radioterapia , Radioterapia de Alta Energia/métodos , Algoritmos , Sobrevivência Celular/efeitos da radiação , Humanos , MatemáticaRESUMO
The thermal neutron distribution in slow and fast neutron beams is usually determined using the foil activation method. In this work a small magnesium walled ionization chamber, in which the inner surface of the wall has been coated with 10B to increase the sensitivity for thermal neutrons, is used to estimate the thermal neutron component of the beam. After calibration and determination of the directional response in a thermal neutron beam a comparison with foil activation at different depths in water was performed to investigate the reliability of the ionization measurements. The chamber was used in a computer controlled water phantom to measure the depth and lateral distribution of the thermal neutron dose. With this arrangement two-dimensional scans of the thermal neutrons could be performed quickly and with high accuracy.