A verification of the Monte Carlo code MCNP for thick target bremsstrahlung calculations.
The bremsstrahlung spectra from thick targets of Be, Al, and Pb are calculated using the Monte Carlo code MCNP (Monte Carlo N-particle). The current version of MCNP (v.4A) incorporates a coupled electron-photon transport scheme that allows the user to estimate the photon fluence produced from primary electron interactions. The simulation parameters are based on bremsstrahlung measurements of 15 MeV electrons incident on thick targets of Be, Al, and Pb at various angles between 0 degree and 90 degrees. The integrated yield and mean energy of each bremsstrahlung spectrum is calculated for the three targets at these angles. For angles less than 60 degrees the integrated yield calculated by MCNP4A is within 6% of measured values for the three targets. Furthermore, predicted mean energy is within 7% of the values derived from measurement for all angles tested. Also compared are the performances of two MCNP4A fluence tallies; a next-event estimator (detector tally) and a track length estimator (cell tally). Timing studies indicate the detector tally will perform the integrated yield calculations to a precision of 1% approximately 10 to 50 times faster than the conventional cell tally for an emission angle of 0 degree.
DeMarco
J J
JJ
Jonsson Comprehensive Cancer Center, Department of Radiation Oncology, University of California, Los Angeles 90024-6951, USA.
Solberg
T D
TD
Wallace
R E
RE
Smathers
J B
JB
D000535:Aluminum; D001608:Beryllium; D007854:Lead; D009010:Monte Carlo Method; D011874:Radiometry / Q000379:methods*; D012542:Scattering, Radiation; D012984:Software
D007854:Lead; D000535:Aluminum; D001608:Beryllium