Abstract
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 the7Li(p, n)7Be and t(d, n)4He reactions and with neutrons from252Cf and239Pu-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.
Original language | English |
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Pages (from-to) | 497-505 |
Number of pages | 9 |
Journal | Health Physics |
Volume | 38 |
Issue number | 4 |
DOIs | |
State | Published - Apr 1980 |
Externally published | Yes |