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Ventura, M.A.
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)
AbstractAbstract
[en] Two radial conduction models, one for steady state and another for unsteady state, in a nuclear power reactor fuel element are developed. The objective is to obtain the temperatures in the fuel pellet and the cladding. The lumped-parameter hypothesis are adopted to represent the system. Both models are verified and their results are compared with similar ones. A method to calculate the conductance in the gap between the UO2 pellet and the clad and its associated uncertainty is included in the steady state model. (author)
[es]
Se desarrollan dos modelos (uno estacionario y otro transitorio) para simular la conduccion radial en un elemento combustible y vaina del elemento. Se adopta la hipotesis de representacion de parametros concentrados. Dichos modelos son verificados y comparados con otros similares. Se incluye en el modelo estacionario un metodo para calcular la conductancia del huelgo existente entre la pastilla de UO2 y la vaina del elemento combustible y la incerteza asociada a su valor. (autor)Original Title
Conduccion de calor radial en un elemento combustible de un reactor de potencia
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1998; 32 p; 9 refs., 6 figs., 3 tabs.
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Puthiyavinayagam, P.; Gopal, S.; Winston, S.J.; Govindarajan, S.; Chetal, S.C.; Bhoje, S.B.
Influence of high dose irradiation on core structural and fuel materials in advanced reactors
Influence of high dose irradiation on core structural and fuel materials in advanced reactors
AbstractAbstract
[en] For the 500 MWe Prototype Fast Breeder Reactor (PFBR), 20% CW D9 has been chosen as the material for fuel clad and wrapper. A peak burnup of 100,000 MWd/t is targeted for the fuel. While experimental data on irradiation behaviour of this material will be generated by irradiation in the test reactor FBTR, presently in operation, correlations have been derived from data available in literature for neutron induced void swelling and creep. The derived data has been used in assessing the deformation in hexagonal wrapper and clad and for optimising core restraint system design. This paper presents results of sensitivity studies carried out in respect of the above data. The parameters considered are hexcan dilation, differential deformation between hexcan and pin bundle and core deformation parameters. It is observed that the fluence parameter has the highest influence on the design parameters. (author)
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International Atomic Energy Agency, Vienna (Austria); 261 p; Aug 1998; p. 153-167; Technical committee meeting on influence of high dose irradiation on core structural and fuel materials in advanced reactors; Obninsk (Russian Federation); 16-19 Jun 1997; 7 refs, 9 figs, 6 tabs
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Report
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Conference
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ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, DEFORMATION, DEPOSITION, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ASSEMBLIES, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, NICKEL ALLOYS, RADIATION EFFECTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, STAINLESS STEELS, STEELS, SURFACE COATING, TEST FACILITIES, TEST REACTORS, TRANSITION ELEMENT ALLOYS
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Toloczko, M.B.; Garner, F.A.
Influence of high dose irradiation on core structural and fuel materials in advanced reactors
Influence of high dose irradiation on core structural and fuel materials in advanced reactors
AbstractAbstract
[en] Four tube-sets constructed from a combination of three lots of HT9 and two heat-treatments were examined after irradiation in FFTF-MOTA at four different temperatures between 400 and 600 deg. C. Diametral measurements indicated that small amounts of swelling occurred at 400 deg. C, with the magnitude of the swelling varying from tube-set to tube set. At 495, 550, and 600 deg. C no indications of swelling were observed. Over a limited stress range that decreased with increasing irradiation temperature, the irradiation creep was found to be proportional to the stress level and mirrored the swelling behavior, confirming the Bo + DS creep model. The creep compliance, Bo, appears to be about half of the observed in austenitic steels, whereas the creep-swelling coupling coefficient D, appears to be comparable to that of austenitics. At the highest stress levels examined, the value of the stress exponent became much greater than 1.0. Higher irradiation temperatures resulted in creep behavior with pronounced thermal creep characteristics: a primary creep transient was observed at the three higher irradiation temperatures and increased in magnitude with increasing irradiation temperature, while a stress exponent between 1.0 and 2.0 was observed at 550 deg. C. (author)
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Source
International Atomic Energy Agency, Vienna (Austria); 261 p; Aug 1998; p. 197-209; Technical committee meeting on influence of high dose irradiation on core structural and fuel materials in advanced reactors; Obninsk (Russian Federation); 16-19 Jun 1997; 17 refs, 7 figs, 3 tabs
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Report
Literature Type
Conference
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Country of publication
ALLOYS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CORROSION RESISTANT ALLOYS, DEFORMATION, EPITHERMAL REACTORS, FAST REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MARTENSITIC STEELS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ADDITIONS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SODIUM COOLED REACTORS, STAINLESS STEELS, STEEL-CR12MOV, STEELS, STRESSES, TEST FACILITIES, TEST REACTORS, TRANSITION ELEMENT ALLOYS, VANADIUM ADDITIONS
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Marengo, J.A.; Ruch, M.; Spinosa, C.
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation
AbstractAbstract
[en] Electromagnetic nondestructive techniques are usually applied to solve many inspection problems in industry. In particular, eddy currents are used for the detection of defects and the characterization of physical properties of metallic materials and components. One such application is the measurement of thickness of non conductive layers on a conducting substrate. A laboratory device for the quantitative determination of those thicknesses was developed at our laboratory. It works in the range from 0 to 100 μm and was calibrated with a micro metre screw. This task involved the design and construction of the sensors their characterization (working frequency, resolution, sensitivity, etc.) and the setup of the mechanical system and the electronic signal generation and measurement circuit. (author)
[es]
Las tecnicas electromagneticas se aplican para resolver diversos problemas en la industria. En metalurgia, la utilizacion de corrientes inducidas permite detectar defectos y caracterizar propiedades fisicas en materiales y componentes. En particular, una de las aplicaciones es la medicion de espesores de capas de recubrimientos aislantes sobre sustrato conductor. Se desarrollo en laboratorio un dispositivo para efectuar un analisis cuantitativo de estos espesores. En la calibracion del mismo se utilizo un tornillo micrometrico. Los espesores a medir estaban en un rango entre 0 y 100 μm. La implementacion de tal sistema involucro el diseno de los sensores de medicion, la construccion de los mismos, el estudio de sus caracteristicas (frecuencia de trabajo, resolucion, sensibilidad, etc.) y la puesta a punto del sistema mecanico y del circuito electronico de generacion de senal y medidas, usados para la realizacion de la tarea. (autor)Original Title
Caracterizacion no destructiva de recubrimientos superficiales sobre materiales no ferromagneticos
Primary Subject
Source
Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Universidad Tecnologica Nacional, Mendoza (Argentina). Facultad Regional; 424 p; 1997; p. 277-281; CORENDE: Regional congress on nondestructive and structural evaluation; CORENDE: Congreso regional de ensayos no destructivos y estructurales; Mendoza (Argentina); 27-30 Oct 1997; 5 refs., 11 figs.
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Miscellaneous
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Conference
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AbstractAbstract
[en] The nuclear power plants steam generators have different types of structural supports. One of these types are the antiseismic supports, which are intended to be under stress only if a seismic event takes place. Nevertheless, the antiseismic supports lugs, that are welded to the steam generator vessel, are subjected to thermal fatigue because of the temperature cycles related with the shut down and start up operations performed during the life of the nuclear power plant. In order to evaluate the stresses that the lugs are subjected to, several strain gages were welded on two supports lugs, positioned at two heights of one of the Embalse nuclear power plant steam generators. In this paper, the instrumentation used and the strain measurements obtained during two start up operations are presented. The influence of the plant start up operation parameters on the lugs strain evolution is also analyzed. (author)
[es]
Los generadores de vapor de las centrales nucleares poseen distintos tipos de soportes estructurales. Uno de esos tipos son los soportes antisismicos, los que deberian soportar cargas solo en el caso en que tenga lugar un evento sismico. A pesar de ello, se encuentran sometidos a un proceso de fatiga termica originado en los ciclos termicos que se producen durante las paradas y puesta en marcha de la central a lo largo de la vida util de la misma. Con el objeto de evaluar estas cargas durante la puesta en marcha de la central, se instrumentaron con extensometros dos soportes antisismicos de uno de los generadores de vapor de la central nuclear Embalse, uno en la zona superior y otro en la zona inferior del mismo. En este trabajo se presenta el tipo de instrumentacion utilizada y los resultados obtenidos durante dos operaciones de puesta en marcha. Se analiza ademas la influencia de los parametros de operacion de la puesta en marcha de la central sobre la evolucion de las deformaciones. (autor)Original Title
Mediciones de deformacion en soportes antisismicos de un generador de vapor en una central nuclear
Primary Subject
Source
Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Universidad Tecnologica Nacional, Mendoza (Argentina). Facultad Regional; 424 p; 1997; p. 333-337; CORENDE: Regional congress on nondestructive and structural evaluation; CORENDE: Congreso regional de ensayos no destructivos y estructurales; Mendoza (Argentina); 27-30 Oct 1997; 1 ref., 7 figs., 1 tab.
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Miscellaneous
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Conference
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Pastorini, A.; Belinco, C.
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation
AbstractAbstract
[en] During the design steps of a fuel bundle for a nuclear reactor, some vibration tests are usually necessary to verify the prototype dynamical response characteristics and the structural integrity. To perform these tests, the known hydrodynamic loop facilities are used to evaluate the vibrational response of the bundle under the different flow conditions that may appear in the reactor. This paper describes the tests performed on a 19 plate fuel bundle prototype designed for a low power research reactor. The tests were done in order to know the dynamical characteristics of the plates and also of the whole bundle under different flow rate conditions. The paper includes a description of the test facilities and the results obtained during the dynamical characterization tests and some preliminary comments about the tests under flowing water are also presented. (author)
[es]
Durante el diseno de un elemento combustible para un reactor nuclear se requiere de la realizacion de ensayos con el objeto de verificar el comportamiento de ese diseno y permitir, de ser necesario, la introduccion de modificaciones al mismo. Para verificar las caracteristicas de respuesta dinamica e integridad estructural, se realizan ensayos de vibraciones que incluyen someter al prototipo a condiciones de circulacion del fluido similares a las que soportara durante la operacion del reactor. Estos ensayos se realizan en facilidades de ensayos conocidas como circuitos hidrodinamicos, que permiten no solo someter el prototipo al flujo de fluido, sino tambien obtener una adecuada caracterizacion de la respuesta del mismo a traves del luso de sensores de distinto tipo. En este trabajo se describen los ensayos realizados sobre un prototipo de elemento combustible de 19 placas destinado a un reactor de investigacion multiproposito de baja potencia. Los ensayos tuvieron como objetivo conocer la respuesta dinamica de las placas individuales y del elemento combustible en su conjunto ante distintas condiciones de caudal de fluido. En el trabajo se incluye una descripcion de las facilidades de ensayo utilizadas y una presentacion de los resultados obtenidos durante la caracterizacion dinamica del prototipo y durante los ensayos con circulacion de fluido. (autor)Original Title
Ensayos hidrodinamicos para verificacion de diseno de un elemento combustible para reactores de investigacion
Primary Subject
Source
Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Universidad Tecnologica Nacional, Mendoza (Argentina). Facultad Regional; 424 p; 1997; p. 407-413; CORENDE: Regional congress on nondestructive and structural evaluation; CORENDE: Congreso regional de ensayos no destructivos y estructurales; Mendoza (Argentina); 27-30 Oct 1997; 4 refs., 12 figs., 4 tabs.
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AbstractAbstract
[en] This paper illustrates developments in and prospects for the application of nuclear science technology in the fields of food and agriculture, industry and environmental protection, in connection with the IAEA's activities
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Secondary Subject
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Hardy, C.J. (ed.); Australian Nuclear Association Inc., Sutherland, NSW (Australia); 332 p; Oct 1997; p. 20; 2ICI: Second international conference on isotopes; Sydney, NSW (Australia); 12-16 Oct 1997; Extended abstract
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Sarkar, T.K.; Chawla, R.; Banik, S.; Chopra, S.J.; Singh, G.; Pant, H.J.; Sreeramakrishnan, P.; Dhar, D.C.; Pushpangathan, P.N.; Sharma, V.K.
Second international conference on isotopes. Conference proceedings
Second international conference on isotopes. Conference proceedings
AbstractAbstract
[en] Gamma scanning of trayed and packed columns is widely used to obtain density profiles and identify on-line problems such as: damaged tray or packing, foaming, flooding, maldistribution, weeping and entrainment, etc. However, scanning of large diameter tray or packed columns requires expertise in handling high intensity gamma sources along with thorough understanding of distillation engineering. Engineers India Limited and the Bhabha Atomic Research Centre undertook scanning of two such large diameter (8.4 m and 7.4 m) trayed and packed refinery vacuum distillation columns and successfully diagnosed the problems and suggested remedial actions. Radiography testing of small diameter columns can be used to confirm gamma scanning results. One such example for ammonia separator column is given
Primary Subject
Source
Hardy, C.J. (ed.); Australian Nuclear Association Inc., Sutherland, NSW (Australia); 332 p; Oct 1997; p. 94-100; 2ICI: Second international conference on isotopes; Sydney, NSW (Australia); 12-16 Oct 1997; 8 figs.
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Miscellaneous
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Conference; Numerical Data
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Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, DATA, DAYS LIVING RADIOISOTOPES, ELECTRON CAPTURE RADIOISOTOPES, EQUIPMENT, HEAVY NUCLEI, HYDRIDES, HYDROGEN COMPOUNDS, INFORMATION, INTERNAL CONVERSION RADIOISOTOPES, IRIDIUM ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MATERIALS HANDLING EQUIPMENT, MINUTES LIVING RADIOISOTOPES, NITROGEN COMPOUNDS, NITROGEN HYDRIDES, NUCLEI, NUMERICAL DATA, ODD-ODD NUCLEI, RADIOISOTOPES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] Isotope tracers have been used successfully in the well-to-well tracer test because of their unique properties, high sensitivity, wide range of choice, easy for in-situ operation and reasonable price thus are getting the broad applications in China recently. Basic methodology has been developed for the design and completion of a test. Methods and equipment for new tracer development and tracer property evaluation have been established. Many field tests were carried out during the past years. As 87% of the total oil reserve are exploited by water drive, water tracer test is much more concerned. Tracers for steam and gas tracing are also reviewed. For water drive, tritiated water (THO) is the most commonly used tracer. Tritiated methanol, tritiated ethanol, 35S tagged thiourea and 60Co tagged K3[Co(CN)6] have been used in some field tests as water tracers; 51Cr-EDTA, 125I-NaI, and some activable tracers (rare earth 1 elements tagged EDTA complex) have also been tried for water tracing in the fractured or a channelling reservoir; the results obtained were encouraging. For steam tracing, THO was used for that of gases, tritium, tritiated methane and krypton (85Kr) were employed. Three field application examples are described in this paper. The first example is about water tracing by use of gamma radiotracers; the second, a typical example of steam tracing by use of THO; and the 1 third introduces the application of activable tracers in water tracing. Current trends of the well-to-well tracer test are the use of partitioning tracers to determine S residual oil saturation of the reservoir, development of new tracers, optimization of the tracer analysis methods, and the development of data interpretation method and software
Primary Subject
Source
Hardy, C.J. (ed.); Australian Nuclear Association Inc., Sutherland, NSW (Australia); 332 p; Oct 1997; p. 112; 2ICI: Second international conference on isotopes; Sydney, NSW (Australia); 12-16 Oct 1997; Extended abstract
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Miscellaneous
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Conference
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHALCOGENIDES, CHROMIUM ISOTOPES, COBALT ISOTOPES, DAYS LIVING RADIOISOTOPES, ELECTRON CAPTURE RADIOISOTOPES, EVEN-ODD NUCLEI, GEOLOGIC DEPOSITS, HOURS LIVING RADIOISOTOPES, HYDROGEN COMPOUNDS, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IODINE ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPE APPLICATIONS, ISOTOPES, KRYPTON ISOTOPES, LIGHT NUCLEI, MINERAL RESOURCES, MINUTES LIVING RADIOISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, OXIDES, OXYGEN COMPOUNDS, PETROLEUM DEPOSITS, RADIOACTIVITY LOGGING, RADIOISOTOPES, RESOURCES, SULFUR ISOTOPES, TRITIUM COMPOUNDS, WATER, WELL LOGGING, WELLS, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The inventory of fusion reactors mainly consists of deuterium and tritium. The amount of tritium of each reactor is equal to the natural inventory of the earth's atmo- and hydrosphere. Elementary tritium (HT) itself is not dangerous to man, for it is hardly dissolved in water, that is neither taken up by human tissues nor metabolized anywhere in our body. In contrast to HT the tritiated water HTO quickly exchanges with any wet surface and with the humidity of air. After an accidental release into the atmosphere the main pathway of intake into the human body is as HTO via the lung; its surface is comparable to a soccer playground. HT released into air will be quickly oxidised within the upper centimetres of the soil when the plume touches the ground. Each soil tested by us until now had oxidized HT, that had shown hydrogenase activity. Neither the biological function nor the catalytic system wee identified yet. The hypothesis of a correlation between hydrogenase activity and soil nitrogen fixation could not be confirmed (nitrogen fixation shows a leakage of hydrogen): nitrogen fixing plants (nodules) do not oxidize HT. The presentation will summarize ten years of work in the laboratory and in the field. A concise picture of the radioecological behaviour of elementary tritium after an accidental release could be obtained. The work was partly done as cooperation within the frame of the EU or within the International Union of Radioecology
Primary Subject
Source
Hardy, C.J. (ed.); Australian Nuclear Association Inc., Sutherland, NSW (Australia); 332 p; Oct 1997; p. 167-178; 2ICI: Second international conference on isotopes; Sydney, NSW (Australia); 12-16 Oct 1997; 5 refs., 2 tabs., 4 figs.
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Miscellaneous
Literature Type
Conference; Numerical Data
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ACCIDENTS, ATMOSPHERIC PRECIPITATIONS, COMPUTERIZED SIMULATION, COORDINATED RESEARCH PROGRAMS, ENVIRONMENTAL TRANSPORT, EXPERIMENTAL DATA, FALLOUT DEPOSITS, ISOTOPIC EXCHANGE, PLUMES, RADIOECOLOGICAL CONCENTRATION, RADIONUCLIDE MIGRATION, SPATIAL DISTRIBUTION, TRITIUM, TRITIUM OXIDES, WATER POLLUTION
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHALCOGENIDES, DATA, DISTRIBUTION, ECOLOGICAL CONCENTRATION, ENVIRONMENTAL TRANSPORT, FALLOUT, HYDROGEN COMPOUNDS, HYDROGEN ISOTOPES, INFORMATION, ISOTOPES, LIGHT NUCLEI, MASS TRANSFER, NUCLEI, NUMERICAL DATA, ODD-EVEN NUCLEI, OXIDES, OXYGEN COMPOUNDS, POLLUTION, RADIOISOTOPES, RESEARCH PROGRAMS, SIMULATION, TRITIUM COMPOUNDS, WATER, YEARS LIVING RADIOISOTOPES
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