Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator

The optimization of a Beam Shaping Assembly design for Boron Neutron Capture Therapy (BNCT), based on a commercial available proton accelerator, has been simulated. The primary goal is to improve the flux of the epithermal neutrons, which is the major drawback in all designed BNCT facilities with po...

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Main Authors: Jacob G. Fantidis, G. Nicolaou
Format: Article
Language:English
Published: Elsevier 2018-12-01
Series:Alexandria Engineering Journal
Online Access:http://www.sciencedirect.com/science/article/pii/S1110016817302478
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spelling doaj-4fdf35f5d7874e5a97d22a10af282a692021-06-02T03:39:37ZengElsevierAlexandria Engineering Journal1110-01682018-12-0157423332342Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton acceleratorJacob G. Fantidis0G. Nicolaou1Department of Electrical Engineering, Eastern Macedonia and Thrace Institute of Technology, Greece; Corresponding author.Department of Electrical and Computer Engineering, Laboratory of Nuclear Technology, Democritus University of Thrace, School of Engineering, Kimmeria Campus, 67100 Xanthi, GreeceThe optimization of a Beam Shaping Assembly design for Boron Neutron Capture Therapy (BNCT), based on a commercial available proton accelerator, has been simulated. The primary goal is to improve the flux of the epithermal neutrons, which is the major drawback in all designed BNCT facilities with portable neutron source, satisfying simultaneously all the other relevant parameters.A BNCT facility has been simulated using the MCNP4B Monte Carlo code. A wide set of material were examined as moderators, while three different materials are used as fast neutron, gamma ray and thermal neutrons filters.Fast neutrons from 9Be(p,n)9B reaction are moderated through the 7LiF and TiF3 moderators and further reduced using 60Ni as fast neutron filter. The undesired gamma rays and thermal neutrons are removed using Bi and Cd filters respectively. The therapeutic efficacy of the proposed facility was calculated through the dosimetric evaluation in a head phantom.According to the results of the calculations the proposed unit satisfies the recommended by IAEA parameters. Only the flux of the epithermal neutrons remains below the recommended threshold, but is significantly improved. Keywords: Boron Neutron Capture Therapy, 9Be(p,n)9B neutron source, Epithermal neutron, MCNP simulations, Beam Shaping Assemblyhttp://www.sciencedirect.com/science/article/pii/S1110016817302478
collection DOAJ
language English
format Article
sources DOAJ
author Jacob G. Fantidis
G. Nicolaou
spellingShingle Jacob G. Fantidis
G. Nicolaou
Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator
Alexandria Engineering Journal
author_facet Jacob G. Fantidis
G. Nicolaou
author_sort Jacob G. Fantidis
title Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator
title_short Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator
title_full Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator
title_fullStr Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator
title_full_unstemmed Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator
title_sort optimization of beam shaping assembly design for boron neutron capture therapy based on a transportable proton accelerator
publisher Elsevier
series Alexandria Engineering Journal
issn 1110-0168
publishDate 2018-12-01
description The optimization of a Beam Shaping Assembly design for Boron Neutron Capture Therapy (BNCT), based on a commercial available proton accelerator, has been simulated. The primary goal is to improve the flux of the epithermal neutrons, which is the major drawback in all designed BNCT facilities with portable neutron source, satisfying simultaneously all the other relevant parameters.A BNCT facility has been simulated using the MCNP4B Monte Carlo code. A wide set of material were examined as moderators, while three different materials are used as fast neutron, gamma ray and thermal neutrons filters.Fast neutrons from 9Be(p,n)9B reaction are moderated through the 7LiF and TiF3 moderators and further reduced using 60Ni as fast neutron filter. The undesired gamma rays and thermal neutrons are removed using Bi and Cd filters respectively. The therapeutic efficacy of the proposed facility was calculated through the dosimetric evaluation in a head phantom.According to the results of the calculations the proposed unit satisfies the recommended by IAEA parameters. Only the flux of the epithermal neutrons remains below the recommended threshold, but is significantly improved. Keywords: Boron Neutron Capture Therapy, 9Be(p,n)9B neutron source, Epithermal neutron, MCNP simulations, Beam Shaping Assembly
url http://www.sciencedirect.com/science/article/pii/S1110016817302478
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