a monte carlo study on the effect of various neutron capturers on dose distribution in brachytherapy with 252cf source

Authors

m m firoozabadi university of birjand

gh izadi vasafi

k karimi-sh university of birjand

m ghorbani

abstract

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  10 b ,  157 gd  and  33 s  neutron capturers and to determine the effect of these materials on dose enhancement rate for  252 cf  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  10 b ,  157 gd  and  33 s  using monte carlo simulation.   results: the difference in the thermal neutron flux rate in the presence of  10 b  and  157 gd  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 258.3 and 476.1 cgy/h/µg for  157 gd  and   10 b , respectively at about 8 cm distance from the source center. def for 33s is equal to one.   conclusion: results show that the magnitude of dose augmentation in tumors containing  10 b  and  157 gd  in brachytherapy with  252 cf  source will depend not only on the capture product dose level, but also on the tumor distance from the source.  33 s  makes dose enhancement under specific conditions that these conditions depend on the neutron energy spectra of source, the  33 s  concentration in tumor and tumor distance from the source.

Upgrade to premium to download articles

Sign up to access the full text

Already have an account?login

similar resources

A Monte Carlo Study on the Effect of Various Neutron Capturers on Dose Distribution in Brachytherapy with 252Cf Source

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 10B, 157Gd and 33S neutron...

full text

A Monte Carlo Study on the Effect of Various Neutron Capturers on Dose Distribution in Brachytherapy with 252Cf Source

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 10B, 157Gd and 33S neutron captu...

full text

Investigation of dose distribution 252Cf Isotron brachytherapy source based on TG-43U1 protocol by Monte Carlo method

 Introduction:The commercial 252Cf sources are too large in size and clinical applications of neutronbrachytherapy (NBT) are limited to a small number of intracavitary treatments of cervical cancers. Recently, under the Cooperative Research and Development Agreement (CRADA) with Isotron Inc., the Oak Ridge National Laboratory (ORNL) encapsulated a new medical 252Cf sources, cal...

full text

Investigation of dose distribution 252Cf Isotron brachytherapy source based on TG-43U1 protocol by Monte Carlo method.

Introduction: The commercial 252Cf sources are too large in size and clinical applications of neutron brachytherapy (NBT) are limited to a small number of intracavitary treatments of cervical cancers. Recently, under the Cooperative Research and Development Agreement (CRADA) with Isotron Inc., the Oak Ridge National Laboratory (ORNL) encapsulated a new medical 252Cf sources, c...

full text

Study of the absorbed dose rate of all rays emitted from the 252Cf brachytherapy source by the Monte Carlo method

The 252Cf brachytherapy source is a spontaneous fission decay source, which is used as a neutron-emitting source. In addition to neutrons emitted from this source, gamma rays are also emitted with the average energy of 1 MeV. In this study, using the Monte Carlo N-Particle code (MCNPX), the absorbed dose rates of the neutrons, the primary gamma and the secondary gamma that generated by thermal ...

full text

the effect of consciousness raising (c-r) on the reduction of translational errors: a case study

در دوره های آموزش ترجمه استادان بیشتر سعی دارند دانشجویان را با انواع متون آشنا سازند، درحالی که کمتر به خطاهای مکرر آنان در متن ترجمه شده می پردازند. اهمیت تحقیق حاضر مبنی بر ارتکاب مکرر خطاهای ترجمانی حتی بعد از گذراندن دوره های تخصصی ترجمه از سوی دانشجویان است. هدف از آن تاکید بر خطاهای رایج میان دانشجویان مترجمی و کاهش این خطاها با افزایش آگاهی و هوشیاری دانشجویان از بروز آنها است.از آنجا ک...

15 صفحه اول

My Resources

Save resource for easier access later


Journal title:
journal of biomedical physics and engineering

جلد ۲۰۱۲، شماره ۱۲، صفحات ۰-۰

Hosted on Doprax cloud platform doprax.com

copyright © 2015-2023