Calculation of reactivity coefficients of the nuclear research reactor TRIGA IAN-R1
AbstractAbstract
[en] In order to evaluate the reactivity coefficients of the TRIGA IAN-R1 core, a simplified core configuration with no control rods and no internal irradiation channels was calculated. The cross-sections set were recalculated running a Wims code for each temperature of fuel, water and the water density. The effective reactivity was calculated using Citation code with a conceptual model and an X-Y-Z calculation in order to avoid buckling recalculations. For the conceptual model of the TRIGA IAN-R1 core, a value of -7.37 pcm/Celcius degrade was obtained for the fuel temperature coefficient; 3.67 pcm/Celsius degrade and -4.28 pcm/Celsius degrade for the temperature coefficient of the moderator and -95.5 pcm/% for the void coefficient.
Original Title
Calculo de coeficientes de reactividad del reactor nuclear de investigacion TRIGA IAN-R1
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Journal Article
Journal
Revista de Investigaciones y Aplicaciones Nucleares; ISSN 2590-7468;
; v. 2; p. 31-34

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Descriptors (DEC)
ANALOG SYSTEMS, COMPUTER CODES, DEVELOPING COUNTRIES, DIMENSIONLESS NUMBERS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, FUNCTIONAL MODELS, IRRADIATION, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, MATERIALS, POOL TYPE REACTORS, REACTIVITY COEFFICIENTS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SIMULATION, SIMULATORS, SOUTH AMERICA, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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