title: Determination of a CR-39 detector response to neutrons from an Am-Be source.
abstract: A comparison of experimental and calculated responses of a CR-39 detector to neutron spectra from an Am-Be source is presented. Code named Neutron_CR-39.F90 has been used to calculate the neutron dose equivalent as well as the track density. Conversion coefficient (sensitivity), between track density in track/cm(2) and neutron dose equivalent in mSv, was calculated and good agreement with experimental data was found. Sensitivity increases linearly with removed layer in the range between 6 μm and 24 μm.
authors.affiliation: University of Kragujevac, Faculty of Science, R. Domanovica 12, 34000 Kragujevac, Serbia.
authors.forename: B
authors.initials: B
authors.lastname: Milenkovic
authors.affiliation: University of Kragujevac, Faculty of Science, R. Domanovica 12, 34000 Kragujevac, Serbia.
authors.forename: N
authors.initials: N
authors.lastname: Stevanovic
authors.affiliation: University of Kragujevac, Faculty of Science, R. Domanovica 12, 34000 Kragujevac, Serbia. Electronic address: nikezic@kg.ac.rs.
authors.forename: D
authors.initials: D
authors.lastname: Nikezic
authors.affiliation: Vinca Institute of Nuclear Sciences, Radiation Protection Laboratory, M.P. Alasa 12-14, Vinca, P.O. Box 522, 11001 Belgrade, Serbia.
authors.forename: D
authors.initials: D
authors.lastname: Kosutic
keywords: CR-39; Chemical etching; Monte Carlo simulation; Neutron; Proton track