Steady-state
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Development of a Steady State Temperature Distribution Code (STD 1.0) for Predicting Thermal-Hydraulics Parameters of MNSR
Abstract: A steady-state temperature distribution code has been developed using Visual Basic 6.0 programming language for the estimation of steady-state temperature distribution in an averaged fuel element of Miniature Neutron Source Reactor. The STD 1.0 code is composed of three parts: Main Menu Window which shows the title of the code, picture of the Nigeria Research Reactor-1 in operation and the link to the other two windows; Radial Temperature Distribution Window, …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 2, 2013 · pp. 1–13 Read article