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Sainz M, E.
Instituto Mexicano del Petroleo, Instituto de Investigaciones Electricas, Instituto Nacional de Investigaciones Nucleares (Mexico)1996
Instituto Mexicano del Petroleo, Instituto de Investigaciones Electricas, Instituto Nacional de Investigaciones Nucleares (Mexico)1996
AbstractAbstract
[en] The updating of the instruments as the operation console of the TRIGA Mark III Salazar Reactor is based on the use of a personal computer that works as data acquisition and control device. The power changes on the reactor have been made through the inserting or extraction of four control rods, that they are operated by mechanisms based in alternate current motors. That is with the object to handling each of the bars and so avoiding too the degradation about the performance of the computer of process. Also it is using four drives of smart kind which do the basic duties for generating the control signals and verifying the sensors state of the limits in continuous form. The computer and drivers are organized as a ring net using the serial port R S-232. The computer of process sends the orders and the identification of destination instrument throughout the net. (Author)
Original Title
Manejador digital de los motores de AC de las barras de control de un reactor nuclear de Investigaciones
Primary Subject
Source
1996; 4 p; Instituto de Investigaciones Electricas; Cuernavaca (Mexico); 8. Seminar of the IMP-IIE-ININ on technological specialties; 8. Seminario IMP-IIE-ININ sobre especialidades tecnologicas; Cuernavaca (Mexico); 26 Jun 1996
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
COMPUTERS, CURRENTS, DIGITAL COMPUTERS, ELECTRIC CURRENTS, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MICROCOMPUTERS, OPERATION, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Cuevas V, D.; Sainz M, E.; Ortiz V, J., E-mail: delfy.cu@gmail.com
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 filtered venting of the containment has been adopted in European countries to mitigate the consequences derived from the excess pressure of the containment during a severe accident. When venting has taken place, the fission products are released directly into the environment, unless a filter is placed in the path of the same, so various types of filters are used to trap the fission products. The containment venting filters currently installed use different filtering technologies that involve more than one medium. Those who use water as the first stage of filtration are called wet systems, are equipped with additional stages to eliminate water drops and emissions of fine aerosols, and may even be equipped with an element that contains certain means of absorption for the gaseous iodine species filtration. Other designs, based on deep bed filtration as the main retention stage, called dry filters; use metal fiber, ceramic or sand filtration media to trap aerosols. The present work evaluates the hydraulic characteristics of the sand bed type filter designed by EDF as a candidate to be installed in the containment of the BWR Mark II (primary containment type of the Laguna Verde nuclear power plant). The evaluation of the sand bed filter was performed using the OpenFOAM open source software package. Models of each zone of the filtering device were generated and by means of a series of parametric calculations of computational fluid mechanics, the relevant hydrodynamic characteristics of the device were obtained, such as pressure drops against mass flow and pressure fields and velocity under different operating conditions. On the other hand, the validation of the sand bed filter model was made when comparing the results of experimental tests carried out in a sand column of the PITEAS program (1985-1986) against the simulation in OpenFOAM. The results obtained are very close to those obtained experimentally. (Author)
Original Title
Analisis de la implementacion de un filtro tipo lecho de arena para el venteo de una central nuclear
Primary Subject
Source
Sep 2017; 15 p; Sociedad Nuclear Mexicana; Ciudad de Mexico (Mexico); 28. SNM Annual Congress; 28. Congreso Anual de la SNM; Ciudad de Mexico (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; Ciudad de Mexico (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
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
AEROSOLS, COLLOIDS, COMPUTER CODES, DESIGN, DISPERSIONS, ELEMENTS, ENRICHED URANIUM REACTORS, EVALUATION, FLUID MECHANICS, HALOGENS, HYDROGEN COMPOUNDS, ISOTOPES, MATERIALS, MECHANICS, NONMETALS, NUCLEAR FACILITIES, OXYGEN COMPOUNDS, POWER, POWER PLANTS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTORS, SEPARATION PROCESSES, SOLS, SORPTION, TESTING, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Reyes G, A. A.; Sainz M, E.; Ortiz V, J., E-mail: alejandroantonioreyess@gmail.com
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] Since the Chernobyl nuclear accident, European nuclear power plants have opted to install filters in the containment vent pipes, whose function is to help mitigate the consequences of a severe accident, by means of the controlled depressurization of the containment passively through of a containment filtering vent system. These systems are designed to relieve the internal pressure of containment by deliberately opening pressure relief devices, either a valve or rupture disk during a severe accident and being channeled to the filtering unit. In this work, the hydraulic response of a liquid gas washing filtration system is evaluated, since this information is necessary to estimate the effect of the increase of the containment pressure on the venting capacity of the vent pipes. Through CFD simulation, using the programs with open source license CaeLinux-2014 and OpenFoam, the hydrodynamic characteristics of the Multi-Venturi system were obtained for the washing of the gases coming from the containment, which could be included in the general model of the vent pipe. Representative models of the venturi tubes of each concentric sector that are part of the washing system were generated and by parametric calculations the average mass expense established by each venturi was estimated, according to its dimensions and depth to which is located inside the tank. In the same way, the pressure and mass expense required to activate each concentric sector was calculated according to the pressure and mass load from the containment, in order to estimate the maximum expenditure that is established through the filter. The velocity profiles and the characteristic pressure at which each sector operates were also calculated, as well as the local and global discharge pressure drop. (Author)
Original Title
Analisis de un filtro multiventuri para el venteo del contenedor primario de un reactor nuclear
Primary Subject
Secondary Subject
Source
Sep 2017; 14 p; Sociedad Nuclear Mexicana; Ciudad de Mexico (Mexico); 28. SNM Annual Congress; 28. Congreso Anual de la SNM; Ciudad de Mexico (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; Ciudad de Mexico (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
Record Type
Miscellaneous
Literature Type
Conference
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
Cuevas V, D.; Sainz M, E.; Ortiz V, J., E-mail: delfy.cu@gmail.com
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] The filtered venting of the containment has been adopted in European countries to mitigate the consequences of excess pressure containment during a severe accident. When venting has taken place, the fission products are released directly into the environment, unless a filter on the same path is placed, so that various types of filters are used to trap the fission products. The venting filters of the containment currently installed use different filtration technologies that involve more than one medium. Those using water as the first stage of filtration are called wet systems and are equipped with additional steps to remove water drops and fine aerosols emissions. And even they may also be equipped with an element containing certain absorption means for the filtration of gaseous iodine species. Other designs based on filtration of deep bed as the primary retention step; called dry filters, use filtration media of metal fiber, ceramic or sand to trap aerosols. This paper evaluates the hydraulic characteristics of the filter sand bed type designed by EDF as a candidate to be installed in the containment of BWR Mark II (type of primary containment of the nuclear power plant of Laguna Verde). The evaluation of filter sand bed type was performed using the software package of open source OpenFOAM. Models of each zone of the filtered device were generated and through a series of parametric calculations of computational fluid mechanics relevant hydrodynamic characteristics of the device were obtained, such as pressure drops against mass flow rate and pressure fields and speed at different operating conditions. On the other hand, the model validation of the sand bed filter when comparing the results of experimental tests on a sand column of PITEAS program (1985-1986) against OpenFOAM simulation was realized. The results are very close to those obtained experimentally. (Author)
Original Title
Calculo hidrodinamico de un filtro tipo lecho de arena usado en los sistemas de venteo de la contencion
Primary Subject
Source
Sep 2015; 15 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
COLLOIDS, COMPUTER CODES, DESIGN, DISPERSIONS, ELEMENTS, ENRICHED URANIUM REACTORS, EVALUATION, HALOGENS, HYDROGEN COMPOUNDS, ISOTOPES, MATERIALS, MECHANICS, NONMETALS, NUCLEAR FACILITIES, OXYGEN COMPOUNDS, POWER PLANTS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTORS, SEPARATION PROCESSES, SIMULATION, SOLS, TESTING, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Ruiz C, M.A.; Rivero G, T.; Celis del Angel, L.; Sainz M, E.; Molina, G., E-mail: marc@nuclear.inin.mx
International Radiation Protection Association (IRPA) (France); Sociedad Mexicana de Seguridad Radiologica A.C. (SMSR), Mexico D.F. (Mexico); Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Organismo Internacional de Energia Atomica (OIEA), Vienna (Australia); Federacion de Radioproteccion de America Latina y el Caribe (FRALC), Zacatecas (Mexico); Organizacion Panamericana de la Salud (OPS), Washington, D.C. (United States)2006
International Radiation Protection Association (IRPA) (France); Sociedad Mexicana de Seguridad Radiologica A.C. (SMSR), Mexico D.F. (Mexico); Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Organismo Internacional de Energia Atomica (OIEA), Vienna (Australia); Federacion de Radioproteccion de America Latina y el Caribe (FRALC), Zacatecas (Mexico); Organizacion Panamericana de la Salud (OPS), Washington, D.C. (United States)2006
AbstractAbstract
[en] Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote form. (Author)
Original Title
Sistema automatizado de control de efluentes liquidos radiactivos de pacientes sometidos a terapia en hospitales de medicina nuclear (SACEL)
Primary Subject
Secondary Subject
Source
2006; 10 p; 1. american congress of the IRPA; Retos y tendencias para el continente americano respecto a la proteccion radiologica, la seguridad nuclear y el ambiente; Acapulco, Gro. (Mexico); 3-8 Sep 2006; 7. regional congress of radiological and nuclear safety; Retos y tendencias para el continente americano respecto a la proteccion radiologica, la seguridad nuclear y el ambiente; Acapulco, Gro. (Mexico); 3-8 Sep 2006; 24. annual meeting of the SMSR; Retos y tendencias para el continente americano respecto a la proteccion radiologica, la seguridad nuclear y el ambiente; Acapulco, Gro. (Mexico); 3-8 Sep 2006; 17. annual congress of the SNM; Retos y tendencias para el continente americano respecto a la proteccion radiologica, la seguridad nuclear y el ambiente; Acapulco, Gro. (Mexico); 3-8 Sep 2006
Record Type
Miscellaneous
Literature Type
Conference
Report Number
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BUILDINGS, DAYS LIVING RADIOISOTOPES, DIMENSIONLESS NUMBERS, INFORMATION, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, ISOTOPES, MATERIALS, MEDICAL ESTABLISHMENTS, MEDICINE, NUCLEI, ODD-EVEN NUCLEI, RADIOACTIVE MATERIALS, RADIOACTIVE WASTES, RADIOISOTOPES, WASTES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Reyes G, A. A.; Sainz M, E.; Ortiz V, J., E-mail: alejandroantonioreyess@gmail.com
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] From the nuclear accident of Chernobyl, the European nuclear power plants have chosen to install filters on the venting pipes of the containment, whose function is to help to mitigate the consequences of a severe accident, by controlled depressurization of the containment passively through a filtered venting of the containment system. These systems are designed to relieve the internal pressure of the containment by means of the deliberate opening of pressure relief devices, either a valve or rupture disc during a severe accident and be channeled to the filter unit. In this paper the hydraulic response of a filter system of gases washing by liquid is evaluated, due to this information is necessary to estimate the effect that has the pressure increase of the contention on the discharge capacity of the venting pipes. By simulation of computational of fluid dynamics with the programs: CAELINUX-2014 and OpenFOAM, the hydrodynamic characteristics of the Multi Venturi System for gases washing from the containment, which could be included in the general model of the venting pipe, were obtained. Representative models of the Venturi tubes of each concentric area that forming the washing system were generated; and using parametric calculations the average mass flow rate established through each venturi, depending on its size and depth in which it is located inside the tank was estimated. Also, the pressure and mass flow rate required to activate each concentric area depending on the pressure and mass load from the containment were calculated, to estimate the maximum flow that is established through the filter. Finally, the velocity profiles and the characteristic pressure at which each area operates as well as the pressure drop of local and global discharge also were calculated. (Author)
Original Title
Calculo hidrodinamico de un filtro tipo lavado en liquidos usados en los sistemas de venteo de la contencion
Primary Subject
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
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gonzalez M, J.L.; Aguilar H, F.; Rivero G, T.; Sainz M, E.
Instituto Nacional de Investigaciones Nucleares. Sindicato Unico de Trabajadores de la Industria Nuclear (Mexico)2000
Instituto Nacional de Investigaciones Nucleares. Sindicato Unico de Trabajadores de la Industria Nuclear (Mexico)2000
AbstractAbstract
[en] In the procedure elaborated to repair the vessel of TRIGA III Mark reactor is required to move toward two tanks of temporal storage the fuel elements which are in operation and the spent fuel elements which are in decay inside the reactor pool. The National Commission of Nuclear Safety and Safeguards (CNSNS) has requested as protection measure that it is carried out a surveillance of the criticality approach of the temporal storages. This work determines the main regulation aspects that entails an experiment of criticality approach, moreover, informing about the results obtained in the developing of this experiments. The regulation aspects are not exclusives for this work in the TRIGA Mark III reactor but they also apply toward any assembling of fissile material. (Author)
Original Title
Normativa aplicable y desarrollo de experimentos de vigilancia de aproximacion a criticidad en el reactor Triga Mark III
Primary Subject
Source
2000; 5 p; 10. ININ-SUTIN Technical and Scientific Congress; Salazar, Estado de Mexico (Mexico); 29-30 Nov 2000
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Miscellaneous
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CONTAINERS, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MONITORING, PLANNING, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, STANDARDS, STORAGE, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Bucio V, F. J.; Sainz M, E.; Ramirez S, R.; Celis del Angel, L.; Palacios H, J., E-mail: fbucio@nuclear.inin.mx
Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Comision Federal de Electricidad (Mexico); Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico); Instituto de Investigaciones Electricas (Mexico); Instituto Nacional de Investigaciones Nucleares (Mexico); Instituto Politecnico Nacional (Mexico); Universidad Autonoma de Zacatecas (Mexico); Universidad Nacional Autonoma de Mexico (Mexico); Academia de Ingenieria de Mexico (Mexico); Asociacion de Jovenes por la Energia Nuclear en Mexico (Mexico); Secretaria de Fomento Turistico, Gobierno del Estado de Yucatan (Mexico). Funding organisation: Areva (France); Bartlett de Mexico (Mexico); GE Energy (United States); Grupo IAI (Mexico); Iberdrola (Spain); Nukem (Germany); Tenex (Russian Federation); Vertek (United States); Westinghouse (United States)2008
Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Comision Federal de Electricidad (Mexico); Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico); Instituto de Investigaciones Electricas (Mexico); Instituto Nacional de Investigaciones Nucleares (Mexico); Instituto Politecnico Nacional (Mexico); Universidad Autonoma de Zacatecas (Mexico); Universidad Nacional Autonoma de Mexico (Mexico); Academia de Ingenieria de Mexico (Mexico); Asociacion de Jovenes por la Energia Nuclear en Mexico (Mexico); Secretaria de Fomento Turistico, Gobierno del Estado de Yucatan (Mexico). Funding organisation: Areva (France); Bartlett de Mexico (Mexico); GE Energy (United States); Grupo IAI (Mexico); Iberdrola (Spain); Nukem (Germany); Tenex (Russian Federation); Vertek (United States); Westinghouse (United States)2008
AbstractAbstract
[en] The cathodic protection is the technique by which the harmful effects of the corrosion for metallic storage tanks can be resisted that they are on the ground. This method causes that all the metallic surface behaves like the cathode of an electrochemical cell. For systems of external cathodic protection, sacrifice anodes can be used or printed current, when sacrifice anodes are used, buried galvanic anodes in the ground are used and connected to the tank, and they are used generally in small tanks. With this technique the anodes are degraded leaving the metallic plate intact. The system proposed for the mathematical simulation of external cathodic protection systems, is an application dedicated to the simulation of a system of anodes for the corrosion protection of diesel containers installed on the ground, that allows to analyze the effects of the resulting current given to the motherboard of the container, that is to say, allows to observe the results before any physical installation and with this of reducing the expenses in the acquisition of unnecessary equipment or its defect, to realize an optimization in the equipment to install to obtain better results. The proposed system was divided in units of sequential processing and not like a whole, the previous thing to allow processing the problem in stages, because it consumes great amount of processing resources and storage during the execution of the same. The aplication was programmed in the programming language of called high level Python. Due to the auxiliary characteristics and units on which it counts, having like basic characteristic the being of open source, reason why it does not require of expensive payments to obtain a license. In the development of the system I am used and unit that allows to visualize controls style Windows, although it is counted on the same version that can be used in operating systems based on Linux. (Author)
Original Title
Herramienta para el modelado de sistemas de proteccion catodica para contenedores diesel de una planta nuclear
Primary Subject
Secondary Subject
Source
2008; 8 p; 19. Annual SNM Congress; Atoms for the development of Mexico; Merida, Yuc. (Mexico); 6-9 Jul 2008; ISBN 978-968-9353-01-1;
; Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion Nuclear, 52045 Ocoyoacac, Estado de Mexico (MX). e-mail: claudio.fernandez@inin.gob.mx

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INIS VolumeINIS Volume
INIS IssueINIS Issue
Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A., E-mail: asrs@nuclear.inin.mx, E-mail: esm@nuclear.inin.mx, E-mail: jare@nuclear.inin.mx
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico (Mexico); Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico); Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico); Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Mexico D.F. (Mexico)2004
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico (Mexico); Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico); Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico); Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Mexico D.F. (Mexico)2004
AbstractAbstract
[en] Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)
Original Title
Interfase visual para la automatizacion del pendulo instrumentado de pruebas Charpy utilizado en el programa de vigilancia de la vasija de reactores de centrales nucleares
Primary Subject
Source
2004; 8 p; 15. Annual Congress of the SNM; Cancun (Mexico); 11-14 Jul 2004; 22. Annual Meeting of the SMSR; Cancun (Mexico); 11-14 Jul 2004; International Joint Meeting Cancun 2004; Cancun (Mexico); 11-14 Jul 2004; International Conjunct Congress Cancun 2004; Cancun (Mexico); 11-14 Jul 2004; 2004 LAS/ANS Symposium; Cancun (Mexico); 11-14 Jul 2004
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
COMPUTER CODES, CONTAINERS, DESTRUCTIVE TESTING, ENRICHED URANIUM REACTORS, FAILURES, IMPACT TESTS, INFORMATION, MATERIALS TESTING, MECHANICAL TESTS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, TESTING, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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