Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code

dc.contributor.authorAdoo, N.A.
dc.contributor.authorNyarko, B.J.B.
dc.contributor.authorAkaho, E.H.K.
dc.contributor.authorAlhassan, E.
dc.contributor.authorAgbodemegbe, V.Y.
dc.contributor.authorBansah, C.Y.
dc.contributor.authorDella, R.
dc.date.accessioned2019-05-10T09:54:37Z
dc.date.available2019-05-10T09:54:37Z
dc.date.issued2011-08
dc.description.abstractThe 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 thermal hydraulic 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 × 10-3 Δk/k to 5.5 × 10-3 Δk/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. © 2011 Elsevier B.V. All rights reserved.en_US
dc.identifier.otherhttps://doi.org/10.1016/j.nucengdes.2011.09.019
dc.identifier.otherVolume 241, Issue 12, Pages 5203-5210
dc.identifier.urihttp://ugspace.ug.edu.gh/handle/123456789/29931
dc.language.isoenen_US
dc.publisherNuclear Engineering and Designen_US
dc.titleDetermination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL codeen_US
dc.typeArticleen_US

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