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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] 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
Country of publication
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INIS VolumeINIS Volume
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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
Celis del A, L.; Rivero, T.; Bucio, F.; Ramirez, R.; Segovia, A.; Palacios, J., E-mail: lina.celis@inin.gob.mx
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico); Sociedad Mexicana de Seguridad Radiologica (SMSR), Ciudad de Mexico (Mexico). Funding organisation: GE Hitachi (United States); Toshiba Westinghouse nuclear (United States); GD Energy Services (Spain); Vertek Industrial Supply Inc. (United States); Nukem (Germany); Grupo IAI (Mexico); Tecnatom (Spain); AIDTSA (Mexico); EERMS (Mexico)2015
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico); Sociedad Mexicana de Seguridad Radiologica (SMSR), Ciudad de Mexico (Mexico). Funding organisation: GE Hitachi (United States); Toshiba Westinghouse nuclear (United States); GD Energy Services (Spain); Vertek Industrial Supply Inc. (United States); Nukem (Germany); Grupo IAI (Mexico); Tecnatom (Spain); AIDTSA (Mexico); EERMS (Mexico)2015
AbstractAbstract
[en] En 2011, Mexico won the Colombian international tender for the renewal of instrumentation and control of the IAN-R1 Reactor, to Argentina and the United States. This paper presents the design criteria and the development made for the new digital control system installed in the Colombian nuclear reactor IAN-R1, which is based on a redundant and diverse architecture, which provides increased availability, reliability and safety in the reactor operation. This control system and associated instrumentation met all national export requirements, with the safety requirements established by the IAEA as well as the requirements demanded by the Colombian Regulatory Body in nuclear matter. On August 20, 2012, the Colombian IAN-R1 reactor reached its first criticality controlled with the new system developed at Instituto Nacional de Investigaciones Nucleares (ININ). On September 14, 2012, the new control system of the Colombian IAN-R1 reactor was officially handed over to the Colombian authorities, this being the first time that Mexico exported nuclear technology through the ININ. Currently the reactor is operating successfully with the new control system, and has an operating license for 5 years. (Author)
Original Title
Nuevo sistema de control digital para la operacion del reactor de investigacion Colombiano IAN-R1
Primary Subject
Source
Sep 2015; 13 p; Sociedad Nuclear Mexicana; Ciudad de Mexico (Mexico); 26. SNM Annual Congress; 26. Congreso Anual de la SNM; Puerto Vallarta, Jalisco (Mexico); 5-8 Jul 2015; 14. SMSR National Congress: nuclear energy, climate change, and safety challenges and radiological protection; 14. Congreso Nacional de la SMSR: energia nuclear, cambio climatico, y retos para la seguridad y proteccion radiologicas; Puerto Vallarta, Jalisco (Mexico); 5-8 Jul 2015; Available from Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mx
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
COLOMBIAN ORGANIZATIONS, DESIGN, DEVELOPED COUNTRIES, DEVELOPING COUNTRIES, ENRICHED URANIUM REACTORS, INTERNATIONAL ORGANIZATIONS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, LICENSES, NATIONAL ORGANIZATIONS, NORTH AMERICA, OPERATION, POOL TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOUTH AMERICA, THERMAL REACTORS, TRADE, 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
Reference NumberReference Number
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
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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
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
INIS VolumeINIS Volume
INIS IssueINIS Issue
Concha, I.A.
Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors1993
Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors1993
AbstractAbstract
[en] This paper presents the neutronic analysis for the conversion of the 10 Kw IAN-R1 research reactor from HEU (90%) to LEU (20%). By changing the number of LEU plates per standard element, five different LEU prototype cores are found acceptable in excess reactivity, and deeper studies with the lowest and highest δK/K% are carried out
Primary Subject
Secondary Subject
Source
Argonne National Lab., IL (United States); 468 p; Jul 1993; p. 358-371; International meeting on reduced enrichment for research and test reactors (RERTR); San Diego, CA (United States); 18-24 Sep 1988; Also available from OSTI as DE94006262; NTIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDES, ELEMENTS, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, MATERIALS, METALS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, THERMAL REACTORS, TRAINING REACTORS, URANIUM, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
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Spin, A.R.; Chesworth, R.H.; West, G.B.
Proceedings of the 1990 International Meeting on Reduced Enrichment for Research and Test Reactors1993
Proceedings of the 1990 International Meeting on Reduced Enrichment for Research and Test Reactors1993
AbstractAbstract
[en] The IAN-R1 reactor was furnished to the Government of Colombia under the 'Atoms for Peace' program by the U.S. Government. The reactor was constructed by Lockheed Aircraft Corporation and achieved initial critically at the Institute for Nuclear Studies in Bogota on 20 January, 1965. The reactor core consists of aluminum clad MTR-type plate fuel elements containing fully-enriched uranium (HEU). The reactor was initially designed to operate at a steady-state power level of 20-kW but has operated at 30-kW for the past several years. The principal applications of the reactor are radioisotope production, radiochemistry, neutron activation analysis, training, and neutron beam physics. Beginning in 1987, a program was initiated to upgrade and modernize the reactor facility. The modernization program has included replacement of the original instrumentation and control system with a new state-of-the-art microprocessor-driven digital system and addition of a new radiation monitoring system
Primary Subject
Secondary Subject
Source
Argonne National Lab., IL (United States); 447 p; Jul 1993; p. 368-385; International meeting on reduced enrichment for research and test reactors; Newport, RI (United States); 23-27 Sep 1990; Also available from OSTI as DE94006497; NTIS
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDES, ELEMENTS, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, MATERIALS, METALS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, THERMAL REACTORS, TRAINING REACTORS, URANIUM, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
Related RecordRelated Record
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