Calculated Fluence Spectra at Neutron Therapy Facilities
- 1 April 1997
- journal article
- Published by Oxford University Press (OUP) in Radiation Protection Dosimetry
- Vol. 70 (1) , 481-484
- https://doi.org/10.1093/oxfordjournals.rpd.a032001
Abstract
The Monte Carlo transport codes LAHET and MCNP were used to calculate energy fluence spectra at three neutron therapy facilities. The results compare very favourably with measured data. Kerma spectra and the ratio of ICRU muscle tissue kerma to A-150 kerma, along with the carbon to oxygen kerma ratio, were determined. Absorbed dose rate calculations are in reasonable agreement with measured values. Use of these codes to study modifications to existing therapy beams is briefly discussed.Keywords
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