Estimation of Na-24 activity concentration in BAEC TRIGA Research Reactor
•Activity concentration for Na-24 at different reactor power level is determined.•For the estimation process several governing equations have been employed.•Coolant flow rate and temperature rise across the core is also determined.•Obtained activity level for Na-24 was found within the safety limit...
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Published in | Results in physics Vol. 7; pp. 975 - 979 |
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Main Authors | , , , , |
Format | Journal Article |
Language | English |
Published |
Elsevier B.V
2017
Elsevier |
Subjects | |
Online Access | Get full text |
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Summary: | •Activity concentration for Na-24 at different reactor power level is determined.•For the estimation process several governing equations have been employed.•Coolant flow rate and temperature rise across the core is also determined.•Obtained activity level for Na-24 was found within the safety limit for restricted areas.
The Bangladesh Atomic Energy Commission (BAEC) TRIGA Research Reactor is a unique nuclear installation of the country generally implemented for a wide variety of research applications and serves as an excellent source of neutron. During reactor operation it is necessary to measure and control the activity concentration of the pool water for fuel element failure detection and for the determination of contamination. The present study deals with the estimation of activity concentration for Na-24 present in water coolant produced as a result of 23Na (n, γ) 24Na reaction. Several governing equations have been employed to estimate the Na-24 activity concentrations theoretically at different reactor power levels including maximum reactor power of 2.4MW. From the obtained result it is ensured that the estimated Na-24 activity of 8.83×10−3μCi/cm3 is not significant enough for any radiological hazard. Thus for ensuring radiological safety issues of the research reactor the assessment performed under the present study has an implication. |
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ISSN: | 2211-3797 2211-3797 |
DOI: | 10.1016/j.rinp.2017.02.014 |