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Markowitz, J.M.; Clayton, J.C.
Bettis Atomic Power Lab., Pittsburgh, Pa. (USA)1970
Bettis Atomic Power Lab., Pittsburgh, Pa. (USA)1970
AbstractAbstract
No abstract available
Primary Subject
Source
Feb 1970; 56 p
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Report
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Cole, E.A.; Peterson, R.S.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1978
Westinghouse Electric Corp., Pittsburgh, PA (USA)1978
AbstractAbstract
[en] This invention relates to an improved continuous calcining apparatus for consistently and controllably producing from calcinable reactive solid compounds of uranium, such as ammonium diuranate, uranium dioxide (UO2) having an oxygen to uranium ratio of less than 2.2. The apparatus comprises means at the outlet end of a calciner kiln for receiving hot UO2, means for cooling the UO2 to a temperature of below 100 deg C and conveying the cooled UO2 to storage or to subsequent UO2 processing apparatus where it finally comes into contact with air, the means for receiving cooling and conveying being sealed to the outlet end of the calciner and being maintained full of UO2 and so operable as to exclude atmospheric oxygen from coming into contact with any UO2 which is at elevated temperatures where it would readily oxidize, without the use of extra hydrogen gas in said means. (author)
Primary Subject
Source
14 Nov 1978; 14 p; CA PATENT DOCUMENT 1042181/A/; Available from Commissioner of Patents, Ottawa-Hull, Canada K1A 0E1
Record Type
Patent
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Artaud, Robert.
CEA, 75 - Paris (France)1975
CEA, 75 - Paris (France)1975
AbstractAbstract
[en] This invention concerns a dry process method for the fabrication of UO2 uranium oxide and a system to use this process. It makes it possible to obtain in a reproducible manner uranium oxide having the requisite physical qualities for easy sintering. The first stage of the process consists in making gaseous uranium hexafluoride with steam in one part of a vessel and the second stage in submitting the UO2F2 oxyfluoride obtained in the first stage to a reduction in another part of the same vessel in order to obtain UO2 uranium oxide
[fr]
La presente invention a pour objets un procede de fabrication d'oxyde d'uranium UO2 par voie seche et un dispositif pour la mise en oeuvre dudit procede. Elle permet d'obtenir d'une maniere reproductible un oxyde d'uranium presentant les qualites physiques necessaires pour qu'on puisse le fritter facilement. Le procede consiste, dans une premiere etape, a faire reagir, dans une premiere region d'un recipient, de l'hexafluorure d'uranium gazeux avec de la vapeur d'eau et, dans une deuxieme etape, a soumettre, dans une deuxieme region du recipient, l'oxyfluorure UO2F2, obtenu lors de la premiere etape, a une reduction de facon a obtenir l'oxyde d'uranium UO2Original Title
Procede et dispositif de fabrication d'oxyde d'uranium UO2 par voie seche
Primary Subject
Source
9 May 1975; 10 p; FR PATENT DOCUMENT 2310315/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
19 Dec 1973; 3 p; GB PATENT DOCUMENT 1341380/B/
Record Type
Patent
Country of publication
Reference NumberReference Number
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Ayer, J.E.; Hins, A.G.; McCuaig, F.D.
Argonne National Lab., Ill. (USA)1970
Argonne National Lab., Ill. (USA)1970
AbstractAbstract
No abstract available
Primary Subject
Source
Jan 1970; 25 p
Record Type
Report
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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Jackson, R.A.; Catlow, C.R.A.
UKAEA Safety and Reliability Directorate, Culcheth1985
UKAEA Safety and Reliability Directorate, Culcheth1985
AbstractAbstract
[en] Results are presented of a new theoretical survey of the energetics of fission Xe in UO2, in which improved gas-lattice potentials are employed, and calculations performed for a range of temperatures. Single gas atom trapping and migration and their solution from underpressurised bubbles is concentrated on. (author)
Primary Subject
Source
Jan 1985; 15 p; To be published in Journal of Nuclear Materials.
Record Type
Report
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Gheorghiu, E.
Central Inst. of Physics, Bucharest (Romania). Inst. of Physics and Nuclear Engineering1987
Central Inst. of Physics, Bucharest (Romania). Inst. of Physics and Nuclear Engineering1987
AbstractAbstract
[en] Using some specific experimental techniques, some aspects of the behaviour of fision gases in the Romanian UO2 are evaluated. (author)
Original Title
Studiul comportarii gazelor de fisiune in bioxidul de uraniu indigen
Primary Subject
Source
1987; 23 p; Published in summary form only.; Thesis (Ph. D.).
Record Type
Report
Literature Type
Thesis/Dissertation
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AbstractAbstract
[en] In order to study densification characteristics of ATR (Advanced Thermal Reactor) type fuel, irradiation experiments have been performed by means of OWL-1 loop in JMTR (Japan Materials Testing Reactor). The experimental results obtained are compared with that obtained from EEI/EPRI, which have performed densification tests under simulated LWR conditions. (orig.)
Primary Subject
Secondary Subject
Source
Letter-to-the-editor.; CODEN: JNUMA.
Record Type
Journal Article
Journal
Journal of Nuclear Materials; ISSN 0022-3115;
; v. 127(1); p. 116-118

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Skomurski, F.N.; Wang, J.W.; Ewing, R.C.; Becker, U., E-mail: frances.skomurski@pnnl.gov, E-mail: jwwang@umich.edu, E-mail: rodewing@umich.edu, E-mail: ubecker@umich.edu2013
AbstractAbstract
[en] Quantum–mechanical techniques were used to determine the charge distribution of U atoms in UO2+x (x ⩽ 0.25) and to calculate activation-energy barriers to oxygen diffusion. Upon optimization, the reduction in unit-cell volume relative to UO2, and the shortest 〈U–O〉 and 〈O–O〉 bond-lengths (0.22 and 0.24 nm, respectively) are in good agreement with experimental data. The addition of interstitial oxygen to the unoccupied cubic sites in the UO2 structure deflects two nearest-neighbor oxygen atoms along the body diagonal of uranium-occupied cubic sites, creating lattice oxygen defects. In (1 × 1 × 2) supercells, the partial oxidation of two U4+ atoms is observed for every interstitial oxygen added to the structure, consistent with previous quantum–mechanical studies. Results favor the stabilization of two U5+ over one U6+ in UO2+x. Calculated activation energies (2.06–2.73 eV) and diffusion rates for oxygen in UO2+x support the idea that defect clusters likely play an increasingly important role as oxidation proceeds
Primary Subject
Source
S0022-3115(11)00836-1; Available from http://dx.doi.org/10.1016/j.jnucmat.2011.09.003; Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
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Villegas de Maroto, Marina; Celora de Lavagnino, Julia; Marajofsky, Adolfo; Leyva, A.G.
Comision Nacional de Energia Atomica, Buenos Aires (Argentina)1981
Comision Nacional de Energia Atomica, Buenos Aires (Argentina)1981
AbstractAbstract
[en] The reprocessing of scrap in the production of UO2 pellets, is important from an economical view-point of the fuel cycle. The recovery method by means of a humid process, tested for UO2 scrap, includes the dissolution of the pellets in a nitric media at boiling point, the precipitation of ammonium diuranates (ADU) and its conversion into UO2 at 600 deg C. The microestructural results and the sintering density of the pellets produced in these tests are compared. It is shown that, although the addition of said UO2 powders impaires the performance of the original mixture produced by the factory, the results thus obtained are, nevertheless, within specifications. This facts show that the mixture would then be able for production. (M.E.L.)
[es]
El reprocesamiento de desechos (''scrap'') en la produccion de pastillas de UO2, reviste importancia desde el punto de vista economico en el ciclo de combustible. El metodo de recuperacion por via humeda ensayada para el ''scrap'' de UO2 comprende la disolucion de pastillas de UO2 en medio nitrico a ebullucion, la precipitacion de diuranato de amonio (ADU) y su conversion a UO2 a 6000C. Se comparan los resultados microestructurales y de densidad de sinterizado de las pastillas obtenidas en estos ensayos. Se observa que, si bien el agregado de los polvos UO2 mencionados desmejora el comportamiento de los polvos originales de fabrica, los valores obtenidos en la mezcla se encuentran dentro de especificaciones. Esto permite inferir que seria, una mezcla apta para ser utilizada en produccion. (M.E.L.)Original Title
Sinterabilidad de mezclas de UO2 de distintas caracteristicas morfologicas
Primary Subject
Record Type
Journal Article
Journal
Energia Nuclear (Buenos Aires); ISSN 0326-0089;
; v. 1(1); p. 42-46

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