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AbstractAbstract
[en] Description of the organization of the Reactor Area at the Instituto de Asuntos Nucleares de Colombia, with objectives and activities in neutronic physics, thermal hydraulic, reactor instrumentation, reactor chemistry, radiological and physical as well as information on the installation equipment and services. The article presents a form of operational reactor facility
Original Title
Reactor
Primary Subject
Source
Instituto de Asuntos Nucleares, Bogota (Colombia); 269 p; ISBN 958-95233-1-5;
; 1989; p. 192-205; IAN; Bogota (Colombia)

Record Type
Book
Country of publication
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AbstractAbstract
[en] The ''Instituto de Asuntos Nucleares'' of Colombia is responsible for IAN-R1 reactor operation, a 20 Kw. nuclear power machine, which became critical the first time on January 20th, 1965. The introduction of nuclear energy in Colombia has allowed to carry out many peaceful applications, where the reactor has played a significant role in support of these programmes. At this time, the main activities are: Educational and training activities; nuclear research; neutron activation analysis; delayed neutron analysis and radioisotopes production for using in agriculture, industry, hydrology and engineering. A description is made of the reactor aspects that have contributed to scientific and technological improvements
Original Title
Reactor nuclear IAN-R1 Caracteristicas tecnicas y aplicaciones
Primary Subject
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Journal Article
Journal
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AbstractAbstract
[en] From the thermal-hydraulics point of view, the nuclear reactor IAN-R1 was analyzed, with special attention to its power upgrade capabilities. In a first calorimetric evaluation, the nominal power was also calibrated as a consequence of a theoretical and experimental matching results
Original Title
Analisis termohidraulico del Reactor IAN-R1
Primary Subject
Record Type
Journal Article
Journal
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AbstractAbstract
No abstract available
Original Title
Reactor IAN-RI del Instituto de Asuntos Nucleares de Colombia - 6 anos de operacion
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Inter-American Nuclear Energy Commission, Washington, D.C; p. 253-262; 1972; Latin American study group meeting on research reactor utilization; Santiago, Chile; 29 Nov 1971
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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
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AbstractAbstract
[en] A distribution was obtained for the thermal neutron flux in the MTR-type fuel elements of the IAN-R1 research nuclear reactor. The flux mapping was carried out with the detector activation technique with the use of Au-197 leaves. The power generated by each fuel element and by the nucleus was determined. Similarly, using the same procedure, the thermal neutron flux was found in the location of the neutron detectors for the control and safety instrumentation used for the operation of the nuclear reactor. This measurement allowed us to diagnose the operating performance of this equipment
Original Title
Parametros fisicos del reactor nuclear IAN-R1
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Country of publication
BARYONS, DISTRIBUTION, ELEMENTARY PARTICLES, ENRICHED URANIUM REACTORS, FERMIONS, HADRONS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, NEUTRONS, NUCLEONS, POOL TYPE REACTORS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SPATIAL DISTRIBUTION, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Sandoval, J.; López, E.; Hernández, A.; Guzmán, M.; Orozco, J.; Gómez, J., E-mail: jsandova@sgc.gov.co
Research Reactors: Safe Management and Effective Utilization. Summary of an International Conference. Companion CD-ROM2017
Research Reactors: Safe Management and Effective Utilization. Summary of an International Conference. Companion CD-ROM2017
AbstractAbstract
[en] This paper describes the thermal power calibration and neutron flux measurement performed in order to have an approach to the IAN-R1 reactor core characterization in the framework of the recently acquired operating license for five years. (author)
Primary Subject
Source
International Atomic Energy Agency, Division of Nuclear Fuel Cycle and Waste Technology, Division of Physical and Chemical Sciences and Division of Nuclear Installation Safety, Vienna (Austria); [1 CD-ROM]; ISBN 978-92-0-105117-2;
; Jul 2017; 7 p; International Conference on Research Reactors: Safe Management and Effective Utilization; Vienna (Austria); 16-20 Nov 2015; IAEA-CN--231-D.10; ISSN 0074-1884;
; Also available on-line: http://www-pub.iaea.org/books/iaeabooks/12207/Research-Reactors-Safe-Management-and-Effective-Utilization and on 1 CD-ROM attached to the printed STI/PUB/1793 from IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; 2 refs., 10 figs.


Record Type
Book
Literature Type
Conference
Country of publication
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Related RecordRelated Record
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External URLExternal URL
Sandoval, J., E-mail: jsandova@sgc.gov.co
History, Development and Future of TRIGA Research Reactors. Companion CD-ROM2016
History, Development and Future of TRIGA Research Reactors. Companion CD-ROM2016
AbstractAbstract
[en] The associated Instrumentation & Control of the Research Nuclear Reactor IAN-R1, located in Colombia, was updated on the year 2012, as a direct result of the initiative by the Colombian Government represented by the Colombian Geological Survey (Servicio Geológico Colombiano). The result of the conversion from Highly-enriched MTR Nuclear fuel into Low-enrichment TRIGA Nuclear fuel guarantees a nuclear reactor that can be operated for several years. The present document presents the Current Technical Status (status of available infrastructure and utilization capabilities, including staff) of the reactor, its success stories, major achievements, and future prospects. (author)
Primary Subject
Source
International Atomic Energy Agency, Division of Physical and Chemical Sciences, Vienna (Austria); [1 CD-ROM]; ISBN 978-92-0-102016-1;
; Jul 2016; p. 17-25; ISSN 0074-1914;
; Also available on-line: http://www-pub.iaea.org/MTCD/Publications/PDF/SupplementaryMaterials/D482/LatinAmericaAndTheCaribbean.pdf; Also available on-line: http://www-pub.iaea.org/books/IAEABooks/Supplementary_Materials/files/10943/100000/History-Development-Future-TRIGA-Research-Reactors and on 1 CD-ROM attached to the printed STI/DOC/010/482 from IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; 7 refs., 8 figs.


Record Type
Book
Country of publication
ACTINIDES, DEVELOPING COUNTRIES, ELEMENTS, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, MATERIALS, METALS, POOL TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOUTH AMERICA, THERMAL REACTORS, TRAINING REACTORS, URANIUM, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
Related RecordRelated Record
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External URLExternal URL
AbstractAbstract
[en] The program to modernize IAN-R1 research reactor control and safety instrumentation has been carried out considering two main aspects: updating safety philosophy requirements and acquiring the newest reactor control instrumentation controlled by computer, following the present criteria internationally recognized, for safety and reliable reactor operations and the latest developments of nuclear electronic technology. The new IAN-R1 reactor instrumentation consist of two wide range neutron monitoring channels, commanded by microprocessor a data acquisition system and reactor control, (controlled by computers). The reactor control desk is providing through two displays; all safety and control signals to the reactor operators; furthermore some signals like reactor power, safety and period signals are also showed on digital bar graphics, which are hard wired directly from the neutron monitoring channels
Original Title
Modernizacion de la instrumentacion de control y seguridad del reactor IAN-R1
Primary Subject
Record Type
Journal Article
Journal
Nucleares; ISSN 0120-7067;
; v. 6(no.11-14); p. 21-32

Country of publication
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Bejarano S, Miguel to; Torres M, Olga L
Universidad Distrital Francisco Jose de Caldas (Colombia)1992
Universidad Distrital Francisco Jose de Caldas (Colombia)1992
AbstractAbstract
[en] For some time the resins of ionic exchange were used for the chemical purification of water. Resins that have double function, are of special interest. They contain a cartridge, ionic channel and cationic channel. Cartridges with mixed channel resins for ionic exchange are used for purification of water in the IAN-R-1 reactor pool. After some time, cartridges lose their ionic exchange capacity and they must be replaced. This investigation is dealing with synthetic resins for ionic exchange, and focuses on standardisation of a method for separation of mixed channels. Favourable conditions were determined for the separation method and recovery of worn-out cartridges of resins for ionic exchange of mixed channel 'Barnstead supercartridges' for water purification
Original Title
Estandarizacion de un metodo de separacion y regeneracion de resina de intercambio ionico de lecho mixto 'Barnstead suprcartridges' que purifica el agua del reactor nuclear IAN R-1 a nivel de laboratorio
Primary Subject
Source
1992; 126 p; Available from Ingeominas; Thesis
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
Country of publication
COOLING SYSTEMS, DEVELOPING COUNTRIES, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, HYDROGEN COMPOUNDS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, ORGANIC COMPOUNDS, ORGANIC POLYMERS, OXYGEN COMPOUNDS, PETROCHEMICALS, PETROLEUM PRODUCTS, POLYMERS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOUTH AMERICA, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
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