Development of a polycarbonate fast neutron dosimeter and comparison with the conventional emulsion dosimeter

The practical application of a polycarbonate as a dosimeter for high energy neutrons is presented. The efficiency of this dosimeter in the energy range of 1-14 MeV was measured with monoenergetic neutrons produced by the 7Li(p,n) 7Be and t(d,n) 4He reactions and with neutrons from 252Cf and 239Pu-Be sources. The electrochemical etching technique for enlarging the damage sites produced by the neutrons, the background of unirradiated polycarbonate foils and the dose thresholds for various energies were investigated. The replacement of the conventional emulsion dosimeter by the polycarbonate dosimeter in the Israel National Badge Service is described. (author)