AbstractAbstract
[en] The present work describes the procedure carried out for the preliminary determination of neutron flux parameters for the nuclear research reactor IAN-R1 (RNI IAN-R1) through the not covered triple monitor method in the nucleus peripheral irradiation position. Using this method, the thermal flux value (φth), the epithermal neutron flux symmetry factor (α) and the ratio between thermal neutron fluxes with respect to the epithermal neutron flux (f) were estimated. Those parameters were obtained by irradiating zirconium (Zr) monitors and a gold-aluminum alloy monitors (Au-Al 0.1% Au), which were irradiated at the G3 and G4 irradiation positions of the RNI IAN-R1. The following values were found for the parameters estimated at an operating power of 30 kW, φth= 2,1 * 1011 cm2 s-1 (variance CV 4%), α = 0,02 (CV 83 %), and f =67 (CV 8 %). The high variance in α could be explained if we consider that the method only uses 3 capture reactions to describe the epithermal neutron spectrum. The variance could be improved by application of multimonitor methods for neutron flux characterization.
Original Title
Implementacion del metodo del triple monitor para la caracterizacion del flujo neutronico del reactor nuclear de investigacion IAN-R1
Primary Subject
Record Type
Journal Article
Journal
Revista de Investigaciones y Aplicaciones Nucleares; ISSN 2590-7468;
; v. 2; p. 35-42

Country of publication
ACTIVATION ANALYSIS, CHEMICAL ANALYSIS, DEVELOPING COUNTRIES, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, NONDESTRUCTIVE ANALYSIS, POOL TYPE REACTORS, RADIATION FLUX, 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
AbstractAbstract
[en] This document presents a historical description of the nuclear research reactor IAN-R1. A contextualization is made about the origin of the reactor within the framework of the Atoms for Peace program, including the technical characteristics and the initial configuration of the core, which was replaced by nuclear fuel MTR technology (90 %) to a new fuel type TRIGA (20 %) (acronyms of material testing reactor and training, research, isotopes, general atomics respectively). In the same way, the characteristics of the two modernization that have been made to the instrumentation and control are presented, the first oriented to the installation of three nuclear channels two of wide range and one power channel, renovation of the control console and the installation of the data acquisition system (DAC) cabinet. The second modernization, which corresponds to the new instrumentation and control of the reactor, is oriented to the change of the control console which supports the control and supervision servers, a nuclear channel NP-1000, printer, four screens of the human interface machine HMI, keyboard of the bar handling system and two keyboards for each of the servers. In addition, the DAC was replaced by the instrumentation cabinet, which includes the reactor protection systems, the redundant control system and the supervision system. The instrumentation and control is characterized by the use of the Ethernet standard to achieve inter-connectivity of the systems, programming of the human machine interface (HMI) using open source code Java, and multi platform, logical separation of functions plying concepts of distributed control and modularity, redundancy, unique failure criteria and independence. The use of the reactor is shown, referring to the irradiation facilities available for irradiation of materials to be studied using the neutron activation analysis (NAA) technique. Likewise, irradiation is planned to support the use of the fission fingerprint dating technique, research and support to educational institutions through technical conferences and a visit to the nuclear facility.
Original Title
Desarrollo de capacidades para la operacion del reactor nuclear IAN-R1
Primary Subject
Record Type
Journal Article
Journal
Revista de Investigaciones y Aplicaciones Nucleares; ISSN 2590-7468;
; v. 2; p. 15-30

Country of publication
ACTIVATION ANALYSIS, CHEMICAL ANALYSIS, DEVELOPING COUNTRIES, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, NONDESTRUCTIVE ANALYSIS, POOL TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, SOUTH AMERICA, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Revista de Investigaciones y Aplicaciones Nucleares; ISSN 2590-7468;
; v. 2; p. 31-34

Country of publication
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
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue