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

José Antonio Sarta,Luis Álvaro Castiblanco

doi:10.32685/2590-7468/invapnuclear.3.2019.509

Abstract

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

Highlights

INTRODUCCIÓNI AN-R1 is a pool-type research reactor that was initially fueled with MTR–HEU enriched to 93 % U-235 [1]
With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel
The results have been compared with the thermal hydraulic analysis carried out by General Atomics (GA), who used the one-dimensional STAT code during the conversion of HEU fuel to LEU TRIGA fuel [3]

Summary

INTRODUCCIÓN

I AN-R1 is a pool-type research reactor that was initially fueled with MTR–HEU enriched to 93 % U-235 [1]. In 1997, General Atomics (GA) converted the HEU fuel to LEU fuel, TRIGA (UzrH1.65) type, and upgraded the reactor power to 100 kW(t) [2]. This paper describes the thermal-hydraulic evaluations made for the IAN-R1 TRIGA reactor operating at 100 kW with cooling from natural convection flow around the fuel elements. The results have been compared with the thermal hydraulic analysis carried out by General Atomics (GA), who used the one-dimensional STAT code during the conversion of HEU fuel to LEU TRIGA fuel [3]. For a single channel of TRIGA IAN-R1 reactor operating at steady conditions, the exit coolant temperature, outlet 2.59 cm coolant velocity, coolant flow rate, maximum wall tempe2.54 cm rature and fuel temperature are calculated. 14.0 cm CON code [4]

CALCULATIONS

RESULTS

CONCLUSIONS