(1) Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai, 400085, India;(2) Reactor Projects Division, Bhabha Atomic Research Centre, Mumbai, 400085, India;(3) Tarapur Atomic Power Station III, Tarapur, 415605, India;
Abstract:
CdZnTe detector was used to monitor the radioactivity at several locations of primary heat transport (PHT) system of the Tarapur
Atomic Power Station-III & IV reactor during shut down as well as operating condition of the reactor. Dose measurements at
the same locations were also carried out using a teletector. MCNP code was used to simulate the detector efficiency for the
required counting geometry. The efficiencies were then used to convert the experimental count rates (cps) to corresponding
activity concentration (Bq/mL) of different radionuclides in coolant water. The total dose rates in these locations were also
calculated by summing up the simulated dose rates of individual γ ray energy. The simulated and the measured total dose rates were found to be in reasonably good agreement.