Abstract
Plastic track detectors have been developed for the measurement of neutron fluences and high gamma doses. The calibration of a CA80–15 Cellulose Nitrate Track Detector coated with ‘Lithium Tetra Borate’ for thermal and epi-thermal neutrons has been done. The results have been compared with those obtained by using other methods. Various plastics have been tested and applied for the measurement of high gamma doses in a reactor core. Finally, the results about the thermal neutron fluences, and gamma doses in the thermal column and the fuel elements respectively of Pakistan Research Reactor (PARR) have been given.
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