An experimental testing of coolant flow rate and velocity in the core of Nigeria Research Reactor-1 Online publication date: Fri, 04-Sep-2015
by S.A. Agbo; Y.A. Ahmed; I.O.B. Ewa; M. Abubakar; M.S. Anas
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 9, No. 2, 2015
Abstract: This paper describes experiments to understand the behaviour of nuclear reactors' thermo-hydraulic parameters allow improved model predictions, contributing to their safety. The Nigeria Miniature Neutron Source Reactor called Nigeria Research Reactor-1 (NIRR-1) is a tank-in-pool type reactor with 90.2% enriched uranium as fuel, and light water as moderator and coolant. The core is cooled by light water natural convection. The reactor core assembly, surrounded by beryllium reflectors, is located at the bottom of the reactor vessel. The NIRR-1 has no installed device to measure the core mass flow rate. In this work, experiments were performed at different power levels to monitor some thermo-hydraulic parameters like core mass flow rate, coolant velocity, mass flux, density and Reynolds number in the core of NIRR-1. These experiments confirm the efficiency of natural circulation in removing the heat produced in the reactor core by nuclear fission.
Existing subscribers:
Go to Inderscience Online Journals to access the Full Text of this article.
If you are not a subscriber and you just want to read the full contents of this article, buy online access here.Complimentary Subscribers, Editors or Members of the Editorial Board of the International Journal of Nuclear Energy Science and Technology (IJNEST):
Login with your Inderscience username and password:
Want to subscribe?
A subscription gives you complete access to all articles in the current issue, as well as to all articles in the previous three years (where applicable). See our Orders page to subscribe.
If you still need assistance, please email subs@inderscience.com
Our Blog 
Follow us on Twitter 
Visit us on Facebook