Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
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)...
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Veröffentlicht in: | Nuclear engineering and design 2011-12, Vol.241 (12), p.5203-5210 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | 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. |
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ISSN: | 0029-5493 1872-759X 1872-759X |
DOI: | 10.1016/j.nucengdes.2011.09.019 |