Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.013 seconds
AbstractAbstract
[en] 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.
Original Title
Calculos de temperatura y flujo de calor para el canal de maxima potencia del reactor de investigacion TRIGA IAN-R1
Primary Subject
Source
Available on line: https:www.sgc.gov.co
Record Type
Journal Article
Journal
Revista de Investigaciones y Aplicaciones Nucleares; ISSN 2590-7468;
; v. 3; p. 36-39

Country of publication
DEVELOPING COUNTRIES, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HYDRAULICS, INTERNATIONAL ORGANIZATIONS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, MECHANICS, NATIONAL ORGANIZATIONS, POOL TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOUTH AMERICA, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue