Fast neutron dosimetry with CR-39 using electrochemical etching

F. Fernández, C. Domingo, C. Baixeras, E. Luguera, M. Zamani, M. Debeauvais

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7 Citations (Scopus)


A Monte Carlo method is used in order to calculate the response (tracks⋯cm-2 ⋯ μSv-1) of a fast neutron dosemeter, composed of a polyethylene radiator and CR-39 plastic track detector, to monoenergetic neutron beams at normal incidence and taking into account the electrochemical etching conditions. The method is applied to neutrons having energies in the range 0.08-10 MeV. The total number of protons emerging from the radiator is calculated, as well as their energetic and angular distribution. Detection efficiency as a function of proton energy and angle is taken into account. The theoretical calculation is compared with experimental results obtained for Am-Li and Pu-Be sources for protonic equilibrium radiator thicknesses. © 1991.
Original languageEnglish
Pages (from-to)467-470
JournalInternational Journal of Radiation Applications and Instrumentation. Part
Issue number1-4
Publication statusPublished - 1 Jan 1991


  • CR-39
  • detection efficiency
  • electrochemical etching
  • Monte Carlo method
  • Neutron dosimetry
  • neutron response

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