Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor

Abstract

With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic\xa0calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel\xa0to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research in\xa0Colombia, this program was carried out and included training, acquisition of hardware,\xa0software and natural convection flow calculations for the TRIGA IAN-R1 research reactor\xa0operating at 100 kW. The purpose of the study is to validate the steady state thermal\xa0hydraulic analysis that has been carried out by means of the NATCON code. This paper\xa0presents the results of the maximum axial temperature distribution for fuel, clad, and coolant.\xa0In addition, the Bernath critical heat flux with pool water temperature as a parameter\xa0is presented.