Experimental and computational determination of neutron dose equivalent around radiotherapy accelerators.
An experimental and computational investigation of the neutron dose equivalent in the treatment room and maze of various radiotherapy accelerators in Canada was completed. A bubble detector was selected for the bulk of the measurements due to its relative insensitivity to gamma radiation. The rooms and accelerator heads were modelled using the MCNP4B Monte Carlo radiation transport code, modified with a photoneutron patch. The results of the investigation showed generally good agreement between the experiments. Monte Carlo and analytical approximations to the neutron dose equivalent, and suggest that if the analytical approximations are used carefully they may be substituted for more costly experimental or Monte Carlo determinations.
Waller
E J
EJ
SAIC Canada, 60 Queen Street, Suite 1516 Ottawa, Ontario, Canada K1P 5Y7. edward.j.waller@saic.com
Jamieson
T J
TJ
Cole
D
D
Cousins
T
T
Jammal
R B
RB
D001822:Body Burden; D003198:Computer Simulation; D004784:Environmental Monitoring / Q000379:methods; D019544:Equipment Failure Analysis / Q000379:methods*; D008962:Models, Theoretical; D009502:Neutrons; D016273:Occupational Exposure / Q000032:analysis*; D010315:Particle Accelerators / Q000295:instrumentation*; D011829:Radiation Dosage; D011835:Radiation Protection / Q000379:methods*; D011874:Radiometry / Q000379:methods*; D011878:Radiotherapy / Q000295:instrumentation*; D012062:Relative Biological Effectiveness; D015203:Reproducibility of Results; D012680:Sensitivity and Specificity