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Hernandez L, J.
Gobierno del Estado de Mexico, Tecnologico de Estudios Superiores de San Felipe del Progreso, San Felipe del Progreso, Estado de Mexico (Mexico)2014
Gobierno del Estado de Mexico, Tecnologico de Estudios Superiores de San Felipe del Progreso, San Felipe del Progreso, Estado de Mexico (Mexico)2014
AbstractAbstract
[en] In this work a new carbonaceous material is presented with improved adsorption properties obtained by a heart treatment about 5 min from the shell tamarind. It was found that the samples obtained carbonaceous adsorbents are effective in removing Co2+ (41 mg / g) ions in aqueous solutions. These samples were prepared from tamarind shell, urea, ammonium nitrate and water. The solution was subjected to a combustion process at different temperatures. Carbonaceous samples prepared in this manner were characterized by X-ray diffraction, infrared spectroscopy, scanning electron microscopy (Sem) and surface area measurements by Physisorption of N2. Changes in structure, morphology and texture were studied. The results show that this material is of great importance to the applications of adsorption of metal ions. The measurements of specific surface area (Bet) were 2.35 to 203.76 m2 g-1 with pore diameters between 2.31 and 15.63 nm, indicating that the samples obtained are predominantly meso porous. The combustion process of the solution proved to be advantageous to improve the textural properties of the tamarind shell. The obtained carbonaceous material plays an important role in adsorption to remove cobalt in aqueous solutions. (Author)
Original Title
Separacion de cobalto presente en solucion acuosa utilizando cascara de tamarindo como biosorbente
Primary Subject
Secondary Subject
Source
2014; 92 p; Thesis (chem. eng.)
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
Report Number
Country of publication
AMIDES, AMMONIUM COMPOUNDS, CARBONIC ACID DERIVATIVES, CHARGED PARTICLES, CHEMICAL REACTIONS, COHERENT SCATTERING, DIFFRACTION, DISPERSIONS, ELECTRON MICROSCOPY, ELEMENTS, HOMOGENEOUS MIXTURES, HYDROGEN COMPOUNDS, IONS, MATERIALS, METALS, MICROSCOPY, MIXTURES, NITRATES, NITROGEN COMPOUNDS, ORGANIC COMPOUNDS, ORGANIC NITROGEN COMPOUNDS, OXIDATION, OXYGEN COMPOUNDS, PHYSICAL PROPERTIES, SCATTERING, SOLUTIONS, SORPTION, SPECTRA, SPECTROSCOPY, SURFACE PROPERTIES, THERMOCHEMICAL PROCESSES, TRANSITION ELEMENTS
Reference NumberReference Number
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Hernandez L, H.
Universidad Nacional Autonoma de Mexico, Mexico City (Mexico). Facultad de Quimica1997
Universidad Nacional Autonoma de Mexico, Mexico City (Mexico). Facultad de Quimica1997
AbstractAbstract
[en] This work presents development of a code to obtain the thermomechanical analysis of fuel rods in the fuel assemblies inserted in the core of BWR reactors. The code uses experimental correlations developed in several laboratories. The development of the code is divided in two parts: a) the thermal part and b) the mechanical part, extending both the fuel and the cladding materials. The thermal part consists of finding the radial distribution of temperatures in the pellet, from the fuel centerline up to the coolant, along the total active length, considering one and two phase flow in the coolant, as a result of the pressure drop in the system. The mechanical part analyzes the effects of temperature gradients, pressure and irradiation, to which the fuel rod is subjected. The strains produced by swelling, creep and thermal stress in the fuel material are analyzed. In the same way the strains in the cladding are analyzed, considering the effects produced by the pressure exerted on the cladding by pellet swelling, by the pressure caused by fission gas release toward the cavities, and by the strain produced on the cladding by the pressure changes of the system. (Author)
Original Title
Analisis termo-mecanico de elementos combustibles nucleares
Primary Subject
Source
1997; 93 p; Thesis (M. in Sci.).
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The postprandial intestinal hyperemia was studied in conscious and anesthetized rats using the radioactive microsphere technique. Carbohydrate, protein, lipid, and mixed meals, and the vehicle (Tyrode's solution), were placed in the stomach via a gastrostomy tube. In conscious rats, blood flow increased by 40-80% in the duodenum and jejunum 1 h after either a carbohydrate, lipid, protein, or mixed meal. Tyrode's solution produced a comparable hyperemia. Blood flow in the distal bowel segments (ileum, cecum, and colon) was significantly increased only by Tyrode's solution and the carbohydrate meal. The proximal intestinal hyperemia produced by the mixed meal in conscious animals was significantly attenuated by vagotomy yet unaltered by atropine pretreatment. In contrast to the results obtained from conscious rats, the mixed meal did not significantly alter intestinal blood flow in anesthetized animals. The results of this study indicate that the postprandial intestinal hyperemia is much greater in conscious than anesthetized animals. This difference may result from the higher resting blood flows in the latter group. The hyperemic response in conscious animals may be mediated by the vagus nerve
Primary Subject
Record Type
Journal Article
Journal
Country of publication
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Hernandez, L.; Xavier Gabarrell, X.; Vicent, T.
The Third International Meeting on Environmental Biotechnology and Engineering. 21-25 September 2008. Palma de Mallorca. Spain2009
The Third International Meeting on Environmental Biotechnology and Engineering. 21-25 September 2008. Palma de Mallorca. Spain2009
AbstractAbstract
[en] Benzo[a]pyrene (BaP), a persistent organic pollutant included in the polycyclic aromatic hydrocarbons group (PAH), is of environmental concern due to its known carcinogenicity and bioaccumulation potential. Because of its toxic properties, it is included in the european community (EC) and United States Environmental Agency (EPA) priority pollutant list resulting in a much more strict regulation and complex tasks to be accomplished for remediation of PAH contaminated environments. (Author)
Primary Subject
Source
350 p; ISBN 978-84-692-4948-2; ; 2009; p. 242; Graficas Terrasa; Islas Baleares (Spain); 3. International Meeting on Environmental Biotechnology and Engineering; Palma de Mallorca (Spain); 21-25 Sep 2008
Record Type
Book
Literature Type
Conference
Country of publication
BIOTECHNOLOGY, CLIMATIC CHANGE, CONTAMINATION, ENGINEERING, ENVIRONMENT, ENVIRONMENTAL IMPACTS, ENZYMATIC HYDROLYSIS, GROUND WATER, MEETINGS, NUTRIENTS, ORGANIC MATTER, PESTICIDES, POLLUTANTS, POLLUTION, RESOURCES, RISK ASSESSMENT, SOLID WASTES, TOXICITY, WASTE MANAGEMENT, WASTE WATER, WATER QUALITY
Reference NumberReference Number
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INIS IssueINIS Issue
Hernandez, L.; Landez, J.P.
Proceedings of the IAEA Specialists' Meeting on experience and further improvement of in-service inspection methods and programmes of NPPs with particular emphasis on on-line techniques1989
Proceedings of the IAEA Specialists' Meeting on experience and further improvement of in-service inspection methods and programmes of NPPs with particular emphasis on on-line techniques1989
AbstractAbstract
[en] The specifications are reported of an automatic in-service inspection machine (MIS) designed by Intercontrole of France for testing the pressure vessel welded joints, the heat affected zones and the area under the cladding. The methods used include TV checks, ultrasonic testing and gamma radiation testing. Submerged focused probes are used for testing, which considerably reduce inspection times. All data are computer-processed using appropriate software. The systems used in practice, i.e., MIS2 to MIS5 are regularly checked, maintained and calibrated at CEN (Cadarache (FR)). (L.O.). 16 figs., 1 tab., 11 refs
Primary Subject
Source
Ceskoslovenska Komise pro Atomovou Energii, Prague (Czechoslovakia); 445 p; 1989; p. 64-91; IAEA specialists' meeting on experience and further improvement of in-service inspection methods and programmes of NPPs with particular emphasis on on-line techniques; Plzen (Czechoslovakia); 5-9 Jun 1989
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Unspec and SMARTS2 models have been used to estimate the UV spectral irradiance values in Valencia, Spain, and the results of these estimations have been compared with experimental measurements of direct irradiance at normal incidence obtained using an Optronic OL 754 in the 300-400 nm range. The relative RMSD and MBD parameters have been used to estimate the deviations of the modelled values with respect to the experimental values. The results indicate that the deviations are smaller when the SMARTS2 model is used with the appropriate aerosol coefficients. (author)
Primary Subject
Source
Workshop on ultraviolet radiation exposure, measurement and protection; Oxford (United Kingdom); 18-20 Oct 1999; Country of input: Hungary
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Alonso V, G.; Hernandez L, H.
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac (Mexico)1991
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac (Mexico)1991
AbstractAbstract
[en] On the basis of the library structure of the RECORD code a method to generate the neutron cross sections by means of the ENDF-B/IV database and the NJOY code has been developed. The obtained cross sections are compared with those of the current library which was processed using the ENDF-B/III version. (Author)
Original Title
Generacion de la biblioteca de secciones eficaces de neutrones para el codigo Record del Sistema de Administracion de Combustible (FMS)
Primary Subject
Source
Nov 1991; 290 p; INIS-MX-RI--1634
Record Type
Report
Report Number
Country of publication
BORON 10, CADMIUM 113, CARBON, CRITICALITY, CROSS SECTIONS, ELASTIC SCATTERING, EUROPIUM 154, FISSION, FUEL MANAGEMENT, HOMOGENIZATION METHODS, HYDROGEN, INELASTIC SCATTERING, NEUTRON SPECTRA, OXYGEN, PLUTONIUM ISOTOPES, REACTOR LATTICES, REACTORS, SAMARIUM 149, SILVER 107, THORIUM 232, URANIUM ISOTOPES, XENON 135, ZIRCONIUM
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BORON ISOTOPES, CADMIUM ISOTOPES, CALCULATION METHODS, ELECTRON CAPTURE RADIOISOTOPES, ELEMENTS, EUROPIUM ISOTOPES, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, HEAVY NUCLEI, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, MANAGEMENT, METALS, MINUTES LIVING RADIOISOTOPES, NONMETALS, NUCLEAR MATERIALS MANAGEMENT, NUCLEAR REACTIONS, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, RADIOISOTOPES, RARE EARTH NUCLEI, SAMARIUM ISOTOPES, SCATTERING, SECONDS LIVING RADIOISOTOPES, SILVER ISOTOPES, SPECTRA, SPONTANEOUS FISSION RADIOISOTOPES, STABLE ISOTOPES, THORIUM ISOTOPES, TRANSITION ELEMENTS, XENON ISOTOPES, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
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Alonso V, G.; Hernandez L, H.
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac (Mexico)1991
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac (Mexico)1991
AbstractAbstract
[en] The present work is the complement of the IT.SN/DFR-017 report in which the structure and the generation of the library of the Thermos code is described. In this report the comparison among the values of the cross sections that has the current library of the Thermos code and those generated by means of the ENDF-B/NJOY it is shown. (Author)
Original Title
Biblioteca de secciones eficaces de neutrones del codigo Thermos
Primary Subject
Source
Oct 1991; 154 p; INIS-MX-RI--1660
Record Type
Report
Report Number
Country of publication
BARYONS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, COMPUTER CODES, ELEMENTARY PARTICLES, ELEMENTS, ENERGY RANGE, EVALUATION, FERMIONS, HADRONS, HOURS LIVING RADIOISOTOPES, INDIUM ISOTOPES, INFORMATION, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, METALS, NUCLEAR REACTIONS, NUCLEI, NUCLEONS, ODD-EVEN NUCLEI, RADIOISOTOPES, SEMIMETALS, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
No abstract available
Primary Subject
Source
Short note.
Record Type
Journal Article
Literature Type
Numerical Data
Journal
Physica Status Solidi. A, Applied Research; ISSN 0031-8965; ; v. 54(2); p. K99-K101
Country of publication
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Hernandez L, H.; Ortiz V, J.
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico (Mexico); Sociedad Nuclear Mexicana, Mexico D.F. (Mexico); Sociedad Mexicana de Seguridad Radiologica A.C., Mexico D.F. (Mexico)2005
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico (Mexico); Sociedad Nuclear Mexicana, Mexico D.F. (Mexico); Sociedad Mexicana de Seguridad Radiologica A.C., Mexico D.F. (Mexico)2005
AbstractAbstract
[en] The pilot plant of fuel production of the National Institute of Nuclear Research (ININ) provided to the Laguna Verde Nuclear Power Plant (CNLV) four fuel assemblies type GE9B. The fuel irradiation was carried out in the unit 1 of the CNLV during four operation cycles, highlighting the fact that in their third cycle the four assemblies were placed in the center of the reactor core. In the Nuclear Systems Department (DSN) of the ININ it has been carried out studies to evaluate their neutron performance and to be able to determine the exposure levels of this fuels. Its also outlines the necessity to carry out a study of the thermomechanical behavior of the fuel rods that compose the assemblies, through computational codes that simulate their performance so much thermal as mechanical. For such purpose has been developing in the DSN the FETMA code, together with the codes that compose the system Fuel Management System (FMS), which evaluates the thermomechanical performance of fuel elements. In this work were used the FETMA and FEMAXI codes (developed by JAERI) to study the thermomechanical performance of the fuel elements manufactured in the ININ. (Author)
Original Title
Evaluacion termomecanica de los ensambles combustibles fabricados en el ININ
Primary Subject
Source
2005; 8 p; 16. Annual Congress of the SNM; Oaxaca 2005. Energia Nuclear del Siglo XXI; Oaxaca (Mexico); 10-13 Jul 2005; 23. Annual Meeting of the SMSR; Oaxaca 2005. Energia Nuclear del Siglo XXI; Oaxaca (Mexico); 10-13 Jul 2005
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
BWR TYPE REACTORS, COMPUTER CODES, DATA, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FABRICATION, FUEL ELEMENTS, FUELS, HEAT TREATMENTS, INFORMATION, MANAGEMENT, MATERIALS, MATERIALS WORKING, NUCLEAR MATERIALS MANAGEMENT, NUMERICAL DATA, POWER REACTORS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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