Radiation dosimetry and medical physics calculations using MCNP 5

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Title: Radiation dosimetry and medical physics calculations using MCNP 5
Author: Redd, Randall Alex
Abstract: Six radiation dosimetry and medical physics problems were analyzed using a beta version of MCNP 5 as part of an international intercomparison of radiation dosimetry computer codes , sponsored by the European Commission committee on the quality assurance of computational tools in radiation dosimetry . Results have been submitted to the committee , which will perform the inter -code comparison and publish the results independently . A comparison of the beta version of MCNP 5 with MCNP 4C2 is made , as well as a comparison of the new Doppler broadening feature . Comparisons are also made between the *F8 and F6 tallies , neutron tally results with and without the use of the S (a ,b ) cross sections , and analytically derived peak positions with pulse height distributions of a Ge detector obtained using the beta version of MCNP 5 . The following problems from the study were examined : Problem 1 was modeled to determine the near -field angular anisotropy and dose distribution from a high dose rate 192Ir brachytherapy source in a surrounding spherical water phantom . Problem 2 was modeled to find radial and axial dose in an artery wall from an intravascular brachytherapy 32P source . Problem 4 was modeled to investigate the response of a four -element TLD -albedo personal dosimeter from neutrons and /or photons . Significant differences in neutron response with S (a ,b ) cross sections compared to results without these cross sections were found . Problem 5 was modeled to obtain air kerma backscatter profiles for 150 and 200 kVp X -rays upon a water phantom . Air kerma backscatter profiles were determined along the apothem and diagonal of the front face of the phantom . A comparison of experimental results is also made . Problem 6 was modeled to determine indirect spectral and energy fluences upon two neutron detectors within a calibration bunker . The largest indirect contribution was found to come from low energy neutrons with an average angle of 47o where 0o is a plane parallel to the floor . Problem 7 was modeled to obtain pulse height distributions for a germanium detector . Comparison of analytically derived peaks with peak positions in the spectra are made . An examination of the Doppler broadening feature is also included .
URI: http : / /hdl .handle .net /1969 .1 /467
Date: 2004-09-30

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Radiation dosimetry and medical physics calculations using MCNP 5. Available electronically from http : / /hdl .handle .net /1969 .1 /467 .

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