Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
2011 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 241, 5303-5210 p.Article in journal (Refereed) Published
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, 5303-5210 p.
Other Physics Topics
Research subject Applied Nuclear Physics
IdentifiersURN: urn:nbn:se:uu:diva-251873DOI: 10.1016/j.nucengdes.2011.09.019OAI: oai:DiVA.org:uu-251873DiVA: diva2:807896