Literature DB >> 18697553

On the production of neutrons in laminated barriers for 10 MV medical accelerator rooms.

A Facure1, A X da Silva, L A R da Rosa, S C Cardoso, G F S Rezende.   

Abstract

When space limitations are primary constraints, laminated barriers with metals can be an option to provide sufficient shielding for a radiotherapy treatment room. However, if a photon clinical beam with end point energy of 10 MeV or higher interacts with the metal inside the barriers neutrons are ejected and can result in an exposure problem inside and outside the vault. The empirical formulae existing in the literature to estimate neutron dose equivalents beyond laminated barriers do not take into account neutron production for spectra below 15 MV. In this work, the Monte Carlo code MCNP was used to simulate the production and transport of photoneutrons across primary barriers of 10 MV accelerator treatment rooms containing lead or steel, in order to obtain the ambient dose equivalents produced by these particles outside the room and in the patient plane. It was found that the neutron doses produced are insignificant when steel is present in the primary barriers of 10 MV medical accelerators. On the other hand, the results show that, in all cases where lead sheets are positioned in the primary barriers, the neutron ambient dose equivalents outside the room generally exceed the shielding design goal of 20 microSv/week for uncontrolled areas, even when the lead sheets are positioned inside the treatment room. Moreover, for laminated barriers, the photoneutrons produced in the metals are summed with the particles generated in the accelerator head shielding and can represent a significant component of additional dose to the patients. In this work, it was found that once lead sheets are positioned inside the room, the neutron ambient dose equivalents can reach the value of 75 microSv per Gray of photon absorbed dose at the isocenter. However, for all simulated cases, a tendency in the reduction of neutron doses with increasing lead thickness can be observed. This trend can imply in higher neutron ambient dose equivalents outside the room for thinner lead sheets. Therefore, when a medical accelerator treatment room is designed with laminated barriers to receive equipment with an end point energy equal to or higher than 10 MeV, not only the required shielding thickness for photon radiation attenuation should be considered, but also the dose due to photoneutrons produced in the metal, which may involve an increase of the lead thickness or even the use of neutron shielding.

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Year:  2008        PMID: 18697553     DOI: 10.1118/1.2940192

Source DB:  PubMed          Journal:  Med Phys        ISSN: 0094-2405            Impact factor:   4.071


  4 in total

1.  Does concrete composition affect photoneutron production inside radiation therapy bunkers?

Authors:  Asghar Mesbahi; Ali-Asghar Azarpeyvand; Hamid Reza Khosravi
Journal:  Jpn J Radiol       Date:  2011-12-17       Impact factor: 2.374

2.  Production of neutrons in laminated barriers of radiotherapy rooms: comparison between the analytical methodology and Monte Carlo simulations.

Authors:  Gabriel Fonseca da Silva Rezende; Luiz Antonio Ribeiro Da Rosa; Alessandro Facure
Journal:  J Appl Clin Med Phys       Date:  2014-11-08       Impact factor: 2.102

3.  An analysis of the regulatory program of quality audits in radiotherapy in Brazil from 1995 to 2007.

Authors:  Eduardo de Paiva; Luiz A R da Rosa; Ricardo R A Brito; Lidia V de Sá; Ana C M Dovales; Delano V S Batista; Ricardo A Giannoni; Alexandre F Velasco
Journal:  J Appl Clin Med Phys       Date:  2011-01-30       Impact factor: 2.243

4.  A fast Monte Carlo code for proton transport in radiation therapy based on MCNPX.

Authors:  Keyvan Jabbari; Jan Seuntjens
Journal:  J Med Phys       Date:  2014-07
  4 in total

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