Bucio V, F. J.; Celis del Angel C, L.; Palacios H, J. C., E-mail: francisco.bucio@inin.gob.mx
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico); Latin-American Section of the American Nuclear Society (LAS/ANS), La Grange Park, IL (United States). Funding organisation: GE Hitachi (United States); Nukem (Germany); Rosatom (Russian Federation)2017
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico); Latin-American Section of the American Nuclear Society (LAS/ANS), La Grange Park, IL (United States). Funding organisation: GE Hitachi (United States); Nukem (Germany); Rosatom (Russian Federation)2017
AbstractAbstract
[en] The Instituto Nacional de Investigaciones Nucleares (ININ) participated in an international tender published by the Colombian Geological Service for the modernization of the Nuclear Reactor Control Console Ian-R1, the participating institutions were: General Atomics (USA), INVAP (Argentina) and ININ (Mexico). The proposal made by the ININ had an important characteristic, the independence of the manufacturer, since it was a project based on modular elements. One of the elements was the Human-Machine Interface (HMI), where the development was proposed under the Free Software (Gnu-GLP) scheme. Java was the programming language on which the HMI was developed to operate the nuclear reactor in Bogota, Colombia. The instrumentation that allows the interaction with the sensors and/or actuators is based on the use of PLC's (programmable logic controllers) with which the computers of the HMI communicate through a local network using the Mod bus protocol over Ethernet. (Author)
Original Title
Diseno del HMI para la operacion de un reactor nuclear de investigacion
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Sep 2017; 9 p; Sociedad Nuclear Mexicana; Ciudad de Mexico (Mexico); 28. SNM Annual Congress; 28. Congreso Anual de la SNM; Mexico City (Mexico); 18-21 Jun 2017; 2017 LAS/ANS Symposium: new technologies for a nuclear power expansion program; Simposio de la LAS/ANS 2017: nuevas tecnologias para un programa de expansion de potencia nuclear; Mexico City (Mexico); 18-21 Jun 2017; 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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Miscellaneous
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Conference
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AbstractAbstract
[en] With cooperation of the International Atomic Energy Agency (IAEA) and the Department of Energy (DOE) of the United States, several calculations and tasks related to the waste disposal of spent MTR fuel enriched nominally to 93% were carried out for the conversion of the IAN-R1 Research Reactor from MTR-HEU fuel to TRIGA-LEU fuel. In order to remove the spent MTR-HEU fuel of the core and store it safely a program was established at the Instituto de Ciencias Nucleares y Energias Alternativas (INEA). This program included training, acquisition of hardware and software, design and construction of a decay pool, transfer of the spent HEU fuel elements into the decay pool and his final transport to Savannah River in United States. In this paper are presented data of activities calculated for each relevant radionuclide present in spent MTR-HEU fuel elements of the IAN-R1 Research Reactor and the total activity. The total activity calculated takes in consideration contributions of fission, activation and actinides products. The data obtained were the base for shielding calculations for the decay pool concerning the storage of spent MTR-HEU fuel elements and the respective dosimetric evaluations in the transferring operations of fuel elements into the decay pool
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International conference on nuclear data for science and technology; Santa Fe, NM (United States); 26 Sep - 1 Oct 2004; (c) 2005 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Conference
Journal
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ACTINIDES, COLOMBIAN ORGANIZATIONS, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM, FUELS, ISOTOPE ENRICHED MATERIALS, MANAGEMENT, MATERIALS, METALS, NATIONAL ORGANIZATIONS, NUCLEAR REACTIONS, RADIOACTIVE WASTE MANAGEMENT, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RIVERS, SURFACE WATERS, URANIUM, WASTE DISPOSAL, WASTE MANAGEMENT
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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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Miscellaneous
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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
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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
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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
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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
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AbstractAbstract
[en] Geriatric oncology is defined by the multidimensional and multidisciplinary approach of the elderly cancer patients. Autonomy, beneficence, non maleficence and justice are the four fundamental principles on which are based the treatment objectives and practical management of these patients. The Comprehensive Geriatric Assessment is the most used tool to detect the functional problems in these elderly patients. The standard oncologic managements of cancer is applies to these patients. However treatment plan and geriatric interventions must be adapted to each individual characteristics of the patients.Thus a strong interdependence between oncologic and geriatric teams is warranted. This implies specific teaching programs during initial medical studies and in the setting of continuous medical education. Furthermore, such wold wide teaching programs may help to the implementation of Geriatric Oncology. In the Geriatric Oncology Program in Lyon we have developed a specific miniassessement to be practiced in an oncologic setting. Geriatric data were obtained by the version of the geriatric multidimensional assessment tool, which we have called minimal comprehensive geriatric assessment” or mini-CGA. This procedure has been designed to collect information on several major domains including medical (co-morbidity), functional, cognitive, affective, social, and environmental aspects. It is essentially based on a very careful medical examination. We also used other evaluation tools previously validated in elderly people. Dependence was measured using three tools: Katz’s Activities of Daily Living (ADLs) scale that focuses on six basic activities of daily living (bathing, dressing, toile ting, transferring, continence, and feeding); Lawton’s Instrumental Activities of Daily Living (IADLs) scale that appraises more complex activities essential for independence in community residence; and the Karnofsky Performance scale (KPS) that is widely used in the oncology setting to subjectively appreciate performance status. Folstein’s Mini Mental State Examination (MMSE) was used to evaluate patient cognitive status. Depressive symptoms were detected with the Geriatric Depression Scale (GDS). Nutritional status was assessed through the Mini-Nutritional Assessment (MNA). The Performance-Oriented Assessment of Mobility instrument provided information on patient physical ability and fall risk. Co morbidity, that corresponds to all medical conditions a patient may have, excluding the disease of primary interest, was assessed using the Cumulative Illness Rating Scale-Geriatrics (CIRS-G). This scale classifies co morbid events by organ system affected, and rates their severity from 0 to 4, with a grading similar to that of the Common Toxicity Criteria scale (none, mild, moderate, severe, extremely severe/life-threatening). This scale has 14 organ system categories and collects information such as the total number of categories involved, total score, severity index (total score/total number of categories involved), the number of categories at level 3 severity, the number of categories at level 4 severity. We also assessed biological functions such as hemoglobin, white blood cell count and differential, creatinine clearance, serum albumin level. Mini-CGA is performed by a multidisciplinary team, including a geriatric ian, a medical oncologist (geriatrics certified), a social worker, a dietician, a physiotherapist, a pharmacist and a research nurse. Each mini-CGA evaluation lasts from ninety to one hundred and twenty minutes. At the end of the procedure, both the geriatric ian and the oncologist draw up an inventory of the different problems identified, and propose an individualized intervention program with specific advice on cancer treatment options
Original Title
Practice of geriatric oncology in the setting of a comprehensive cancer center
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Source
Sociedad de Oncologia Medica y Pediatrica del Uruguay, Montevideo (Uruguay); 44 p; Dec 2004; 1 p; 8. Uruguayan congress of Oncology; 8. Congreso Uruguayo de Oncologia; Montevideo (Uruguay); 2-4 Dec 2004; Available in abstract form only, full text entered in this record; Available from: www.urucan.org.uy/iah/.../octavo_congreso_oncologia_programa.pdf; Lecture
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Miscellaneous
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Conference
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ADULTS, AGE GROUPS, AGED ADULTS, ANIMALS, AZOLES, BIOLOGICAL MATERIALS, BLOOD, BODY FLUIDS, CARBOXYLIC ACIDS, COLOMBIAN ORGANIZATIONS, DEVELOPING COUNTRIES, DISEASES, GLOBINS, HETEROCYCLIC ACIDS, HETEROCYCLIC COMPOUNDS, HUMAN POPULATIONS, IMIDAZOLES, IMINES, LATIN AMERICA, MAMMALS, MAN, MATERIALS, MINORITY GROUPS, NATIONAL ORGANIZATIONS, ORGANIC ACIDS, ORGANIC COMPOUNDS, ORGANIC NITROGEN COMPOUNDS, PERSONNEL, PIGMENTS, POPULATIONS, PORPHYRINS, PRIMATES, PROTEINS, SOUTH AMERICA, VERTEBRATES
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