Gamma Dosimetry Using Red 4034 Harwell Dosimeters in Mixed Fission Neutrons and Gamma Environments

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The radiation tolerance testing of materials or optoelectronic components in a nuclear reactor requires a careful determination of the different components of the mixed gamma-neutron field. While the characterization of the neutron field can be performed using, for example, activation foils and validated by Monte-Carlo computation codes, the experimental measurement of the in-reactor gamma dose rate requires the use of costly ionization chambers. In this paper, we evaluate the possibility of using Red Perspex from Harwell Technologies for routine gamma dosimetry in mixed gamma neutron field. Self-powered gamma detectors and ionization chambers were used as reference dosimeters. We show that the accuracy of the Red 4034 dosimeters is better than 10% in mixed gamma-neutron fields.


Original languageEnglish
Pages (from-to)505-509
JournalIEEE transactions on nuclear Science
Issue number2
Publication statusPublished - 1 Apr 2005


  • Dosimetry, fission reactors, gamma-ray detectors, radiation effects.

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