World TRIGA users conference, 3

Abstract

Experimental and analytical studies have been performed in the IPR-R1 TRIGA Mark-1 reactor at Nuclear Technology Development Center (CDTN), Brazil, to find out the temperature distribution under steady-state conditions as a function of the reactor power. The flow distribution in the cooling channels and the heat-transfer coefficient on the heated surface were obtained experimentally. These results permitted to make the prediction of critical heat flux (CHF), which defines the limit of fuel heat removal.