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
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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
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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
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Gonzalez M, J. L.; Rivero G, T.; Merino C, F. J.; Santander C, L. E., E-mail: francisco.merino@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] As part of the evaluation of the structural integrity of the components of nuclear plants, particularly those applying for life extension is necessary to carry out inspections and nondestructive testing to determine the state meet. In many cases these activities are carried out in areas with high levels of radiation and contamination difficult to access, so that are required to use equipment or robotic systems operated remotely. Among others, the frames and cells of the storage pools for spent fuel are structures subject to a program of tests and inspections, and become relevant because the nuclear power plant of Laguna Verde (NPP-LV) is processing the license to extend the operational life of its reactors. Of non-destructive testing can be used to verify the physical condition of the frames and storage cells, is the remote visual inspection which is a test that allows determine the physical integrity of the components by one or more video cameras designed to applications in underwater environments with radiation, and are used to identify and locate adverse conditions such as ampoules, protuberances, pitting, cracks, stains or buckling, which could affect the three main functions for which the store components are designed: to maintain the physical integrity of spent fuels, store them properly guaranteeing their free insertion and removal, and ensure that the store as a whole meets the criticality criteria that k_e_f_f is less than 0.95 throughout the life of the plant. This paper describes a proposal to carry out the visual inspection of the storage cells of spent fuel from the NPP-LV using a probe including one or more video cameras along with your recorder, and its corresponding control program. It is noted that due to the obtained results, the nuclear power plant personnel can make decisions regarding remedial actions or applying complementary methods to verify that the cells and frames have not lost their physical integrity, or in particular that the cover plates of Boral has not lost its ability to absorb neutrons, using proven methods like Badger or similar. (Author)
Original Title
Propuesta para la inspeccion visual de la integridad de las celdas de almacenamiento de combustible gastado de la Central Laguna Verde (CLV)
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Source
Sep 2015; 14 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
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Guerra C, D. A.; Tovar M, R.; Gonzalez M, J. L.; Segovia de los Rios, A., E-mail: deniwar@gmail.com
Sociedad Nuclear Mexicana (SNM), Mexico D. F. (Mexico); Sociedad Mexicana de Seguridad Radiologica (SMSR), Mexico D. F. (Mexico). Funding organisation: GE, Hitachi (United States); Vertek Industrial Supply Inc. (United States); Nukem (Germany); Iberdrola, Ingenieria y Construccion (Spain); Centro Oncologico de Queretaro (Mexico); ALSA Dosimetria S. de R. L. de C. V. (Mexico); Asesores en Radiaciones, S. A. (Mexico); Grupo IAI (Mexico); Ultra Ingenieria S. A. de C. V. (Mexico); Servicios Integrales para la Radiacion S. A. de C. V. (Mexico)2013
Sociedad Nuclear Mexicana (SNM), Mexico D. F. (Mexico); Sociedad Mexicana de Seguridad Radiologica (SMSR), Mexico D. F. (Mexico). Funding organisation: GE, Hitachi (United States); Vertek Industrial Supply Inc. (United States); Nukem (Germany); Iberdrola, Ingenieria y Construccion (Spain); Centro Oncologico de Queretaro (Mexico); ALSA Dosimetria S. de R. L. de C. V. (Mexico); Asesores en Radiaciones, S. A. (Mexico); Grupo IAI (Mexico); Ultra Ingenieria S. A. de C. V. (Mexico); Servicios Integrales para la Radiacion S. A. de C. V. (Mexico)2013
AbstractAbstract
[en] In the Instituto Nacional de Investigaciones Nucleares (ININ), personnel have been working in the development of wheels mobile robots for the surveillance and supervision of contaminated areas, and for the radioactive material transport. One of these achievements is the wheels mobile robot denominated TRASMAR2, which is sought that works in the tele operated form using net technologies, in particular, using a Web page by means of the client-servant technology. For this, diverse circuits and control programs have been development with the purpose that the robot carries out the movements that are required, being considered the use of sensors to avoid collisions. The different programs have been implemented in different micro controllers, and although the robot was working, is necessary to optimize and to concentrate these programs on a single micro controller. In this work are presented the analysis of the previously implemented programs, as the realized changes, including new programs required to improve the robot operation. As complement, was development and implemented an alternative proposal of the robot's tele operation by means of a Web page using Lab view, which is described in the work. With this proposal tele operate the robot was achieved, although its application is evaluating due to the resources that is consumes. (author)
Original Title
Mejora del funcionamiento del robot movil de ruedas TRASMAR2
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Secondary Subject
Source
Oct 2013; 12 p; Sociedad Nuclear Mexicana; Mexico D. F. (Mexico); 24. SNM Annual Congress: nuclear energy in Mexico, past and future; 24. Congreso Anual de la SNM: energia nuclear en Mexico, pasado y futuro; Queretaro (Mexico); 30 Jun - 3 Jul 2013; 12. SMSR National Congress: culture of radiological protection; 12. Congreso Nacional de la SMSR: cultura de seguridad radiologica; Queretaro (Mexico); 30 Jun - 3 Jul 2013; ISBN 978-607-95174-4-1;
; Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: claudio.fernandez@inin.gob.mx

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