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Padilla, C., E-mail: cristobal.padilla@desy.de2000
AbstractAbstract
[en] HERA-B, an experiment to measure CP violation in the B0→J/ψKS0 decay channel at the HERA proton storage ring at DESY, is a pioneering hadronic B factory using fixed target techniques. In addition to the CP violation measurement, the experiment addresses a wide range of topics in heavy quark physics, complementing the physics accessible at e+e- colliders. The detector design is discussed, putting special emphasis on the needs for the CP violation measurement. Recent commissioning results, from runs using a partially installed detector, are presented
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S0168900200000097; Copyright (c) 2000 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment; ISSN 0168-9002; ; CODEN NIMAER; v. 446(1-2); p. 176-189
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ACCELERATORS, BEAUTY MESONS, BEAUTY PARTICLES, BOSONS, COLLISIONS, COMPOSITE MODELS, CYCLIC ACCELERATORS, DECAY, ELECTRON COLLISIONS, ELEMENTARY PARTICLES, HADRONS, INVARIANCE PRINCIPLES, MATHEMATICAL MODELS, MEASURING INSTRUMENTS, MESONS, PARTICLE DECAY, PARTICLE MODELS, POSITRON COLLISIONS, PSEUDOSCALAR MESONS, STORAGE RINGS, SYNCHROTRONS, WEAK PARTICLE DECAY
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Padilla C, I.
Proceedings of the 4. National Congress of the Mexican Society of Radiological Safety C.A1991
Proceedings of the 4. National Congress of the Mexican Society of Radiological Safety C.A1991
AbstractAbstract
[en] In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program
Original Title
Nuevas recomendaciones del ICRP y el programa ALARA de la Central Laguna Verde
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Sociedad Mexicana de Seguridad Radiologica Asociacion Civil, Mexico City (Mexico); 316 p; 1991; p. 67-77; 4. National Congress of the Mexican Society of Radiological Safety C.A; Oaxaca (Mexico); 6-9 Mar 1991; Country of input: Mexico; 1 tab
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Padilla C, I., E-mail: ipadilla@cfe.gob.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] During the operation of the nuclear power stations there are metals that are subject to condition and agents that cause that these they present indications of intergranular corrosion and for their importance they are subject to a continuous surveillance to assure their integrity. During the time of operation, for the level of indications, it can be necessary the substitution of these. The internal components of the vessel and particularly those of the structure of the reactor core are exposed during the operation to a neutron flow that causes that these they are activated and, in consequence, before an eventual repair it will be necessary to face high radiation levels. At the moment a technique that controls exists and it reduces the growth rate of the indications in the metals and it increases its useful life: the addition of hydrogen. The addition of hydrogen it is an ALARA measure from long term when protecting the internals of the vessel that requires to establish radiological controls in the stage of their application to avoid unnecessary dose to the personnel. The addition of hydrogen to the primary system has as objective to reduce the growth of indications taken place by intergranular corrosion in metals of the reactor core and this is achieved when the electrochemical thresholds are reached. Hydrogen to interacting with the metal surfaces it generates reductive reactions causing in consequence an increment in the concentration of soluble cobalt in the coolant one and an increment in the nitrogen concentration. To reduce the magnitude of the radiological impact that in some NC reach up to factors 10, its are injected to the system noble metals as the rhodium and the platinum, to reduce the concentration of hydrogen to the system and to be below the threshold electrochemical potential necessary to protect the internals of the reactor vessel. The external and internal operational experience generated on this protection technique to the internals of the vessel and of the radiological behavior when applying them, its allowed to settle down strategies in the Laguna Verde Central to control and to reduce the magnitude of the radiological increment in the primary steam lines in both units during the initial period of application. The radiological effects by the addition of hydrogen and of the noble metals, and its incorporation sequence to the reactor are the one reason of this work. (Author)
Original Title
Analisis radiologico por la adicion de hidrogeno y metales nobles en los reactores de la Central Laguna Verde
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2006; 8 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
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Hohlmann, M.; Padilla, C.; Tesch, N.; Titov, M., E-mail: hohlmann@fit.edu2002
AbstractAbstract
[en] High-Energy Physics experiments are currently entering a new era which requires the operation of gaseous particle detectors at unprecedented high rates and integrated particle fluxes. Full functionality of such detectors over the lifetime of an experiment in a harsh radiation environment is of prime concern. New classes of gaseous detectors such as large-scale straw-type detectors, Micro-pattern Gas Detectors, and resistive plate chambers--each with their own specific aging characteristics--have evolved since the first workshop on wire chamber aging was held at LBL, Berkeley in 1986. The 2001 workshop provided a forum to review the progress since 1986 in understanding aging effects and to exchange recent experiences. A summary of the main results reported at the 2001 workshop is presented providing a systematic review of aging effects in state-of-the-art detectors
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S0168900202014638; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment; ISSN 0168-9002; ; CODEN NIMAER; v. 494(1-3); p. 179-193
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Boychenko, S.; Aguilera-Padilla, C.; Dragu, M.
Proceedings of the 15th International Conference on Accelerator and Large Experimental Physics Control Systems ICALEPCS 20152016
Proceedings of the 15th International Conference on Accelerator and Large Experimental Physics Control Systems ICALEPCS 20152016
AbstractAbstract
[en] During the last two years, CERNs Large Hadron Collider (LHC) and most of its equipment systems were upgraded to collide particles at an energy level twice higher compared to the first operational period between 2010 and 2013. System upgrades and the increased machine energy represent new challenges for the analysis of transient data recordings, which have to be both dependable and fast. With the LHC having operated for many years already, statistical and trend analysis across the collected data sets is a growing requirement, highlighting several constraints and limitations imposed by the current software and data storage ecosystem. Based on several analysis use-cases, this paper highlights the most important aspects and ideas towards an improved, second generation data analysis framework to serve a large variety of equipment experts and operation crews in their daily work. (author)
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Riches, Kathleen (ed.) (Synchrotron Light Source Australia, Melbourne, VIC (Australia)); Australian Synchrotron, Melbourne, VIC (Australia); Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW (Australia); 1225 p; ISBN 978-3-95450-148-9; ; Jan 2016; p. 802-805; ICALEPCS 2015: 15. International Conference on Accelerator and Large Experimental Physics Control Systems; Melbourne, VIC (Australia); 17-23 Oct 2015; Also available online from https://accelconf.web.cern.ch/ICALEPCS2015/; 10 refs., 4 figs.
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Aguilera-Padilla, C.; Boychenko, S.; Dragu, M.
Proceedings of the 15th International Conference on Accelerator and Large Experimental Physics Control Systems ICALEPCS 20152016
Proceedings of the 15th International Conference on Accelerator and Large Experimental Physics Control Systems ICALEPCS 20152016
AbstractAbstract
[en] The Post Mortem service for the CERN accelerator complex stores and analyses transient data recordings of various equipment systems following certain events, like a beam dump or magnet quenches. The main purpose of this framework is to provide fast and reliable diagnostic to the equipment experts and operation crews to help them decide whether accelerator operation can continue safely or whether an intervention is required. While the Post Mortem System was initially designed to serve the CERN Large Hadron Collider (LHC), its scope has been rapidly extended to include as well External Post Operational Checks and Injection Quality Checks in the LHC and its injector complex. These new use cases impose more stringent time-constraints on the storage and analysis of data, calling for a migration of the system towards better scalability in terms of storage capacity as well as I/O throughput. This paper presents an overview of the current service, the ongoing investigations and plans towards a scalable data storage solution and API, as well as the proposed strategy to ensure an entirely smooth transition for the current Post Mortem users. (author)
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Riches, Kathleen (ed.) (Synchrotron Light Source Australia, Melbourne, VIC (Australia)); Australian Synchrotron, Melbourne, VIC (Australia); Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW (Australia); 1225 p; ISBN 978-3-95450-148-9; ; Jan 2016; p. 806-809; ICALEPCS 2015: 15. International Conference on Accelerator and Large Experimental Physics Control Systems; Melbourne, VIC (Australia); 17-23 Oct 2015; Also available online from https://accelconf.web.cern.ch/ICALEPCS2015/; 14 refs., 2 figs.
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AbstractAbstract
[en] A study of scaling violations in fragmentation functions is presented. ALEPH data samples enriched in b jets, u, d, s jets and gluon jets, respectively, together with measurements of the longitudinal and transverse inclusive cross sections, are used to extract the fragmentation functions for each flavour. Comparing these measurements to lower energy data (PEP, PETRA and TRISTAN), scaling violations consistent with QCD are observed and a measurement of the strong coupling constant αs(MZ2)=0.127±0.011 is obtained. ((orig.))
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QCD Workshop '94: High energy physics; Montpellier (France); 7-13 Jul 1994
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Padilla, C. I.
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico). Funding organisation: GE Hitachi (United States); Westinghouse Electric (United States); Tecnatom (Spain); Cameco (Canada); Framatome (France); Rosatom (Brazil); IPN, Escuela Superior de Fisica y Matematicas (Mexico); IAEA (Austria); H. Ayuntamiento de la Ciudad y Puerto de Veracruz (Mexico)2022
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico). Funding organisation: GE Hitachi (United States); Westinghouse Electric (United States); Tecnatom (Spain); Cameco (Canada); Framatome (France); Rosatom (Brazil); IPN, Escuela Superior de Fisica y Matematicas (Mexico); IAEA (Austria); H. Ayuntamiento de la Ciudad y Puerto de Veracruz (Mexico)2022
AbstractAbstract
[en] Radiological protection aims to reduce the occurrence of stochastic effects in humans due to exposure to ionizing radiation, where their probability and not their severity is a function of the dose without a threshold, and to avoid deterministic effects where their severity is a function of the dose above a threshold. This work presents a summary of operational protection measures against nuclear events and, which emanate from the knowledge and experiences documented by the International Committee on Radiological Protection (ICRP) in its publication 146, which has currently been made freely accessible, due to the growing tension in Ukraine, involving nuclear aspects. (author)
Original Title
Proteccion radiologica y la seguridad internacional
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Dec 2022; 5 p; Sociedad Nuclear Mexicana; Ciudad de Mexico (Mexico); 33. SNM Annual Congress: nuclear power, the most efficient energy source to mitigate global warming; 33. Congreso Anual de la SNM: energia nuclear, la fuente de energia mas eficiente para mitigar el calentamiento global; Veracruz, Ver. (Mexico); 13-16 Nov 2022
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Padilla C, I., E-mail: ipadilla@cfe.gob.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] To optimize times and movements in a reload project of nuclear fuel in a nuclear plant, where they are programmed more three thousand maintenance activities, modifications, monitoring and inspection in a smaller period to 30 days, and additionally to optimize the individual and collective dose in the same one, turn out to be important challenges where the used strategies must be accompanied of a deep knowledge of the installation in the radiological sense and of the spaces conceptualized in the time. The attention to the detail makes possible that the objectives are fulfilled. During the shutdown of reload 9 of Unit 2 (9RU2) of the nuclear power plant of Laguna Verde, the attention in detail applied in the critical points allowed a saving of dose of 0.7 Sv-person and one deviation of the goal of only +0.85% (smaller to 1% of the goal established like 2 challenge of Sv-person). Analysis of times, movements and training to develop skills in inspection activities in service that requires intervention in the external surface of the reactor vessel to examine the condition of welds, allowed reducing times of execution of 12 to 2 hours. Analysis of the environment and attention to the detail are techniques that allowed optimizing dose in 9RU2 and they were used in the project Power Increase. In this work the strategies of the surroundings and attention in detail applied in 9RU2 would appear and detail attention in the increase of power in the reload 13 Unit 1. (Author)
Original Title
9RU2 Proteccion radiologica, atencion al detalle-EPU
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2008; 6 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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Padilla C, I., E-mail: ipadilla@cfe.gob.mx
Sociedad Mexicana de Seguridad Radiologica A.C. (SMSR), Mexico D.F. (Mexico); Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Mexican Association for Energy Economics (AMEE) (Mexico)2007
Sociedad Mexicana de Seguridad Radiologica A.C. (SMSR), Mexico D.F. (Mexico); Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Mexican Association for Energy Economics (AMEE) (Mexico)2007
AbstractAbstract
[en] In the primary contention of the Laguna Verde central reactors those are located the main components and control and safety systems related directly with the reactor vessel. Space, accesses, location, maneuvers, armor-plating, movements of components and radiological conditions require of a constant attention to maintain the control of the activities during a fuel reload period. Knowledge, analysis, strategies and attention to the detail in the preparation stages and execution of the fuel reload are fundamental to sum up the objectives. The reload stop 12 of the Unit 1, it required a specific attention in the radiation source due to the addition of noble metals and hydrogen to the vessel internals that generated an increment in the soluble elements of Cobalt and that it was reflected in the radiation fields in the primary contention. Movement of armor-plating of the structures of the biological armor-plating demand to establish new strategies in the control of activities for the next fuel reloads. The analysis and control of the relief valves safety of the reactor vessel, of the exchange of the activation mechanisms of the control bars, as well as of the isolation valves of main vapor and of flow control valves of the reactor recirculation system, its required of a particular attention due to their particular radiological environment, in a brief time space. The importance of this work is located in the detail of critical activities to fulfill the established goals, with successes that can be optimized, and improvement areas that require of investigation and analysis for the implementation of new technologies tend toward to the dose optimization. The reload stop 12 of the unit 1 conclude with 2.43 Sv-person in a period of 27.5 days. (Author)
Original Title
Contencion primaria 12RU1 control radiologico
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2007; 8 p; 25. SMSR Annual Meeting Co-sponsored by AMEE; Contribution of nuclear energy to the sustainable development of Latin-America; Cancun, Q.R. (Mexico); 1-5 Jul 2007; 18. Annual SNM Congress; Contribution of nuclear energy to the sustainable development of Latin-America; Cancun, Q.R. (Mexico); 1-5 Jul 2007; 2007 LAS/ANS Symposium; Contribution of nuclear energy to the sustainable development of Latin-America; Cancun, Q.R. (Mexico); 1-5 Jul 2007; ISBN 978-968-9353-00-3; ; Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion Nuclear, 52045 Ocoyoacac, Estado de Mexico (MX). e-mail: svp@nuclear.inin.mx; rbc@nuclear.inin.mx
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Conference; Numerical Data
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