Experimental prediction of departure from nucleate boiling on the IPR-R1 TRIGA nuclear reactor core

Experimental and analytical studies have been performed in the IPR-R1 TRIGA Mark-1 Reactor at Technology Development Center (CDTN), Brazil, to find out the temperature distribution as a function of reactor power under steady-state conditions. Initially some studies were made on flow distribution in the coolant channels and heat transfer coefficient on the heated surface (Mesquita, 2005). These results were used for the prediction of departure from nucleate boiling, which defines the limit of fuel heat removal. This paper describes the methodology used and presents the experimental results. The data show the efficiency of the natural circulation to remove the heat generated in by the fissions the IPR-R1 TRIGA core. (author)