CALCULATED FLUENCE SPECTRA AT NEUTRON THERAPY FACILITIES

Authors
ROSS MA DELUCA PM JONES DTL LENNOX A MAUGHAN RL
Citation
Ma. Ross et al., CALCULATED FLUENCE SPECTRA AT NEUTRON THERAPY FACILITIES, Radiation protection dosimetry, 70(1-4), 1997, pp. 481-484
Citations number
14
Categorie Soggetti
Radiology,Nuclear Medicine & Medical Imaging","Nuclear Sciences & Tecnology
Journal title
Radiation protection dosimetry → ACNP
ISSN journal
01448420
Volume
70
Issue
1-4
Year of publication
1997
Pages
481 - 484
Database
ISI
SICI code
0144-8420(1997)70:1-4<481:CFSANT>2.0.ZU;2-A
Abstract
The Monte Carlo transport codes LAHET and MCNP were used to calculate energy fluence spectra at three neutron therapy facilities. The result s compare very favourably with measured data. Kerma spectra and the ra tio of ICRU muscle tissue kerma to A-150 kerma, along with the carbon to oxygen kerma ratio, were determined. Absorbed dose rate calculation s are in reasonable agreement with measured values. Use of these codes to study modifications to existing therapy beams is briefly discussed .