Open AccessCalculation and benchmark of fluence-to-local skin equivalent dose coefficients for neutrons with FLUKA, MCNP, and GEANT4 Monte-Carlo codes
Author(s) -
Thomas Frosio,
Philippe Bertreix,
N. Menaa,
Samuel Thomas
Publication year - 2021
Publication title -
journal of radiological protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.471
H-Index - 46
eISSN - 1361-6498
pISSN - 0952-4746
DOI - 10.1088/1361-6498/ac057e
Subject(s) - monte carlo method , neutron , radiation protection , physics , fluence , benchmark (surveying) , equivalent dose , nuclear physics , radiation , nuclear engineering , nuclear medicine , radiation transport , neutron transport , computational physics , irradiation , mathematics , medicine , statistics , engineering , geodesy , geography
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.