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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
AbstractAbstract
[en] A brief description of the radiological applications available with high intensity radiation sources is made, preceded by a short historical review of the gamma irradiation plant of the Instituto de Asuntos Nucleares. The most important researches carried out, the services given to industry, hospitals, universities and infrastructure are mentioned. Finally, some of the publications realized in the last years are summarized
Original Title
Facilidad gamma
Primary Subject
Secondary Subject
Source
Instituto de Asuntos Nucleares, Bogota (Colombia); 269 p; ISBN 958-95233-1-5;
; 1989; p. 110-124; IAN; Bogota (Colombia)

Record Type
Book
Country of publication
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
INIS VolumeINIS Volume
INIS IssueINIS Issue
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
INIS VolumeINIS Volume
INIS IssueINIS Issue
External URLExternal URL
AbstractAbstract
[en] The rapid technical development of Colombia over the past years, resulted among others, a considerable increase in the number of measuring instrumentation and testing laboratories, scientific research and metrology centers, in industry, agriculture, public health, education on the nuclear field, etc. IAN is a well organized institution with qualified management, trained staff and reasonably equipped laboratories to carry out tasks as: Metrology, standardization, quality control and maintenance and repair of nuclear instruments. The government of Colombia has adopted a policy to establish and operate through the country maintenance and repair facilities for nuclear instrumentation. This policy is reflected in the organization of electronic laboratories in Bogota-IAN
Original Title
Electronica nuclear
Source
Instituto de Asuntos Nucleares, Bogota (Colombia); 269 p; ISBN 958-95233-1-5;
; 1989; p. 90-101; IAN; Bogota (Colombia)

Record Type
Book
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gonzalez M, J. L.; Rivero G, T.; Sainz M, E., E-mail: joseluis.gonzalez@inin.gob.mx
Sociedad Nuclear Mexicana (SNM), Mexico D. F. (Mexico); Sociedad Mexicana de Seguridad Radiologica (SMSR), Mexico D. F. (Mexico). Funding organisation: GE, Energy (United States); Toshiba (Mexico); Westinghouse (United States); Tenex (Russian Federation); Nukem (Germany); Vertek Industrial Supply Inc. (United States); Grupo IAI (Mexico); Tecnatom (Spain); Iberdrola, Ingenieria y Construccion (Spain)2014
Sociedad Nuclear Mexicana (SNM), Mexico D. F. (Mexico); Sociedad Mexicana de Seguridad Radiologica (SMSR), Mexico D. F. (Mexico). Funding organisation: GE, Energy (United States); Toshiba (Mexico); Westinghouse (United States); Tenex (Russian Federation); Nukem (Germany); Vertek Industrial Supply Inc. (United States); Grupo IAI (Mexico); Tecnatom (Spain); Iberdrola, Ingenieria y Construccion (Spain)2014
AbstractAbstract
[en] Due to the obsolescence of the instrumentation and control system of the nuclear research reactor IAN-R1, the Institute of Geology and Mining of Colombia, IngeoMinas, launched an international convoking for renewal it which was won by the Instituto Nacional de Investigaciones Nucleares (ININ). Within systems to design, the reactor protection system is described as important for safety, because this carried out, among others two primary functions: 1) ensuring the reactor shutdown safely, and 2) controlling the interlocks to protect against operational errors if defined conditions have not been met. To fulfill these functions, the various subsystems related to the safety report the state in which they are using binary signals and are connected to the inputs of two redundant logic wiring circuits called action logics (Al) that are part of the reactor protection system. These Al also serve as logical interface to indicate at all times the status of subsystems, both the operator and other systems. In the event that any of the subsystems indicates a state of insecurity in the reactor, the Al generate signals off (or scram) of the reactor, maintaining the interlock until the operator sends a reset signal. In this paper the design, implementation, verification and testing of circuits that make up the Al 1 and 2 of IAN-R1 reactor is described, considering the fulfillment of the requirements that the different international standards imposed on this type of design. (Author)
Original Title
Diseno de los circuitos de la logica de actuacion del sistema de proteccion del reactor nuclear IAN-R1 de Colombia
Primary Subject
Secondary Subject
Source
Oct 2014; 14 p; Sociedad Nuclear Mexicana; Mexico D. F. (Mexico); 25. SNM Annual Congress; 25. Congreso Anual de la SNM; Boca del Rio, Veracruz (Mexico); 31 Aug - 4 Sep 2014; 13. SMSR National Congress: the nuclear challenges; 13. Congreso Nacional de la SMSR: los retos nucleares: extension de vida, seguridad, percepcion publica y reactores de nueva generacion; Boca del Rio, Veracruz (Mexico); 31 Aug - 4 Sep 2014; life extension, safety, public perception and reactors of new generation; 13. Congreso Nacional de la SMSR: los retos nucleares: extension de vida, seguridad, percepcion publica y reactores de nueva generacion; Boca del Rio, Veracruz (Mexico); 31 Aug - 4 Sep 2014; Available from the 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, DEVELOPING COUNTRIES, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, NATIONAL ORGANIZATIONS, POOL TYPE REACTORS, REACTOR SHUTDOWN, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SHUTDOWN, SOUTH AMERICA, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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
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] 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
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
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