M M Firoozabadi - Department of Physics, Faculty of Sciences, University of Birjand, Birjand, Iran
Gh Izadi Vasafi - Department of Physics, Faculty of Sciences, University of Birjand, Birjand, Iran
K Karimi-sh - Department of Physics, Faculty of Sciences, University of Birjand, Birjand, Iran
M Ghorbani - Biomedical Engineering and Medical Physics Department, Faculty of Medicine, Shahid Beheshti University of Medical Sciences, Tehran, Iran

Background: In neutron interaction with matter and reduction of neutron energy due to multiple scatterings to the thermal energy range, increasing the probability of thermal neutron capture by neutron captures makes dose enhancement in the tumors loaded with these materials.Objective: The purpose of this study is to evaluate dose distribution in the presence of ۱۰B, ۱۵۷Gd and ۳۳S neutron capturers and to determine the effect of these materials on dose enhancement rate for ۲۵۲Cf brachytherapy source.Methods: Neutron-ray flux and energy spectra, neutron and gamma dose rates and dose enhancement factor (DEF) are determined in the absence and presence of ۱۰B, ۱۵۷Gd and ۳۳S using Monte Carlo simulation.Results: The difference in the thermal neutron flux rate in the presence of ۱۰B and ۱۵۷Gd is significant, while the flux changes in the fast and epithermal energy ranges are insensible. The dose enhancement factor has increased with increasing distance from the source and reached its maximum amount equal to ۲۵۸.۳ and ۴۷۶.۱ cGy/h/µg for ۱۵۷Gd and ۱۰B, respectively at about ۸ cm distance from the source center. DEF for ۳۳S is equal to one.Conclusion: Results show that the magnitude of dose augmentation in tumors containing ۱۰B and ۱۵۷Gd in brachytherapy with ۲۵۲Cf source will depend not only on the capture product dose level, but also on the tumor distance from the source. ۳۳S makes dose enhancement under specific conditions that these conditions depend on the neutron energy spectra of source, the ۳۳S concentration in tumor and tumor distance from the source.

Brachytherapy, Neutron Capture, Dose, MCNP