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.
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Acknowledgements
The authors sincerely thank T. P. Chaturvedi, N. Tawde from Radiochemistry Division, Bhabha Atomic Research Centre (BARC) for their contribution in online activity measurement. The authors are also thankful to Dr. V. K. Manchanda, Head Radiochemistry division (BARC) and Dr. R. A. Agrawal from Reactor Projects Division, (BARC) for their guidance and keen interest in this work.
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Chaudhury, S., Agarwal, C., Goswami, A. et al. Determination of radioactivity concentration in the primary coolant channel of a Pressurized Heavy Water Reactor. J Radioanal Nucl Chem 286, 47–54 (2010). https://doi.org/10.1007/s10967-010-0610-9
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DOI: https://doi.org/10.1007/s10967-010-0610-9