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Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
(Ghana Atomic Energy Commission)
(Ghana Atomic Energy Commission)
(Ghana Atomic Energy Commission)
Uppsala University, Disciplinary Domain of Science and Technology, Physics, Department of Physics and Astronomy, Applied Nuclear Physics. (Nuclear Research Group)
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2011 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 241, p. 5303-5210Article in journal (Refereed) Published
Abstract [en]

The PARET/ANL code has been adapted by the IAEA for testing transient behaviour in research reactors since it provides a coupled thermal hydrodynamic and point kinetics capability for estimating thermalhydraulic margins. A two-channel power peaking profile of the Ghana Research Reactor-1 (GHARR-1) has been developed for the PARET/ANL (Version 7.3; 2007) using the Monte Carlo N-Particle code (MCNP) to determine the thermal hydraulic data for reactivity insertion transients in the range of 2.0×10^−3k/k to 5.5×10^−3k/k. Peak clad and coolant temperatures ranged from 59.18 ◦C to 112.36 ◦C and 42.95 ◦C to 79.42 ◦C respectively. Calculated safety margins (DNBR) satisfied the MNSR thermal hydraulic design criteria for which no boiling occurs in the reactor core. The generated thermal hydraulic data demonstrated a high inherent safety feature of GHARR-1 for which the high negative reactivity feedback of the moderator limits power excursion and consequently the escalation of the clad temperature.

Place, publisher, year, edition, pages
2011. Vol. 241, p. 5303-5210
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Other Physics Topics
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Applied Nuclear Physics
Identifiers
URN: urn:nbn:se:uu:diva-251873DOI: 10.1016/j.nucengdes.2011.09.019OAI: oai:DiVA.org:uu-251873DiVA, id: diva2:807896
Available from: 2015-04-25 Created: 2015-04-25 Last updated: 2017-12-04

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CiteExportLink to record
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