Determination of radioactivity concentration in the primary coolant channel of a Pressurized Heavy Water Reactor

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 usi...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry 2010-10, Vol.286 (1), p.47-54
Main Authors: Chaudhury, Sanhita, Agarwal, Chhavi, Goswami, A., Mhatre, Amol, Gathibandhe, Manohar, Dash, S. C.
Format: Article
Language:English
Subjects:
Chemistry
Chemistry and Materials Science
Detectors
Diagnostic Radiology
Dosage
Hadrons
Heavy Ions
Inorganic Chemistry
Nuclear Chemistry
Nuclear engineering
Nuclear Physics
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Physical Chemistry
Radioactivity
Simulation
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Summary: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.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-010-0610-9