Abstract

Attempts have been made to develop solid-state nuclear track detectors (SSNTDs) for the measurement of (a) fast and thermal neutron fluences, and (b) high gamma doses existing around a reactor core and the spent fuel elements of Pakistan Research Reactor (PARR). Special attention has been paid to finding the registration efficiency of a CA80-15 cellulose nitrate track detector coated with lithium tetra borate for thermal and epi-thermal neutrons. Various plastics have been tested and calibrated for the measurement of high gamma doses in the reactor core itself. Also, these detectors have been used in the determination of thermal and epi-thermal neutron fluences and, after shutdown, gamma doses in the thermal column and the core of Pakistan Research Reactor (PARR). The results have been compared with those obtained by using other methods.

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