Abstract
Dose equivalent limits for single organs are recommended by the ICRP (International Commission for the Radiological Protection publication 103). These limits do not lend themselves to be measured. They are assessed by convoluting conversion factors with particle fluences. The Fluence-to-Dose conversion factors are tabulated in the ICRP literature. They allow assessing the organ dose of interest using numerical simulations. In particular, the literature lacks the knowledge of local skin equivalent dose (LSD) coefficients for neutrons. In this article, we compute such values for neutron energies ranging from 1 meV to 15 MeV. We use FLUKA, MCNP and GEANT4 Radiation transport Monte-Carlo simulation codes to perform the calculations. A comparison between these three codes is performed. These calculated values are important for radiation protection studies and radiotherapy applications.
Highlights
Neutron radiation dose estimation is of high interest in radiation protection studies as well as radiotherapy applications
The assessment of local skin equivalent and absorbed dose (LSD) (ICRP116 2010) can be performed using fluence-to-local skin equivalent dose (LSD) Conversion Coefficients referred as ‘LSD-CC’ in the rest of this article. Such conversion coefficients are provided by the International Commission on Radiological Protection (ICRP), in the publication 116 (ICRP116 2010)
The scored quantity is the deposited energy in the scoring volume. This quantity is transformed into the absorbed dose and to the equivalent dose using the neutron radiation weighting factors provided in ICRP92 (2003)
Summary
Neutron radiation dose estimation is of high interest in radiation protection studies as well as radiotherapy applications. The assessment of local skin equivalent and absorbed dose (LSD) (ICRP116 2010) can be performed using fluence-to-LSD Conversion Coefficients referred as ‘LSD-CC’ in the rest of this article. Such conversion coefficients are provided by the International Commission on Radiological Protection (ICRP), in the publication 116 (ICRP116 2010). We compute the LSD-CC values for equivalent and absorbed skin dose using the irradiation scenario geometry presented in the publication 116, Annex G (ICRP116 2010), in order to complete ICRP data. The LSD-CC values for equivalent and absorbed skin dose are computed with three different radiation transport Monte-Carlo calculation codes: FLUKA, GEANT4 and MCNP.
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