Analysis of thermal-hydraulic transients for the Miniature Neutron Source Reactor (MNSR) in Ghana

S. Yamoah, E. H.K. Akaho, B. J.B. Nyarko, M. Asamoah, A. G. Ampong, E. O. Amponsah-Abu

Research output: Contribution to journalArticlepeer-review

2 Citations (Scopus)

Abstract

A mathematical model is presented that permits to simulate the effect of the cooling coils of the pool upper section on the reactor thermal-hydraulic behaviour of Ghana research reactor-1. The model is based on a lumped parameter description solved numerically using Matlab/Simulink tool which is a commercial software package with the capability of modelling dynamical and control systems. The model incorporates fuel grids and cooling coil models as well as radiating energy from the clad. In this model, the reactor tank and the pool is divided into three sections. The model predictions are qualified by comparing the results with experimental data. The effect of cooling the upper section of the pool on reactor thermal-hydraulic parameters using the cooling coil is presented and discussed. It was observed that all maximum values of the reactor thermalhydraulic parameters decrease when the cooling coil power is increased. Good agreement is found between the model predictions and the experimental results.

Original languageEnglish
Pages (from-to)737-745
Number of pages9
JournalResearch Journal of Applied Sciences, Engineering and Technology
Volume3
Issue number8
Publication statusPublished - 2011
Externally publishedYes

Keywords

  • Coolant
  • Cooling coil
  • Lumped parameter
  • Natural convection
  • Tank-in-pool
  • Thermo-hydraulic

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