Title of article :
Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
Author/Authors :
Adoo، نويسنده , , N.A. and Nyarko، نويسنده , , B.J.B. and Akaho، نويسنده , , E.H.K. and Alhassan، نويسنده , , E. and Agbodemegbe، نويسنده , , V.Y. and Bansah، نويسنده , , C.Y. and Della، نويسنده , , R.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2011
Pages :
8
From page :
5203
To page :
5210
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.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2011
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1591733
Link To Document :
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