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
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