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Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
- Source :
-
Nuclear Engineering & Design . Dec2011, Vol. 241 Issue 12, p5203-5210. 8p. - Publication Year :
- 2011
-
Abstract
- Abstract: 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 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. [Copyright &y& Elsevier]
Details
- Language :
- English
- ISSN :
- 00295493
- Volume :
- 241
- Issue :
- 12
- Database :
- Academic Search Index
- Journal :
- Nuclear Engineering & Design
- Publication Type :
- Academic Journal
- Accession number :
- 69534961
- Full Text :
- https://doi.org/10.1016/j.nucengdes.2011.09.019