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Laloui, L.; Francois, B.
Ecole Polytechnique Federale de Lausanne (EPFL), Lausanne (Switzerland). Funding organisation: Federal Office of Topography (swisstopo), Wabern (Switzerland)
Mont Terri Project - Proceedings of the 10 Year Anniversary Workshop2007
Ecole Polytechnique Federale de Lausanne (EPFL), Lausanne (Switzerland). Funding organisation: Federal Office of Topography (swisstopo), Wabern (Switzerland)
Mont Terri Project - Proceedings of the 10 Year Anniversary Workshop2007
AbstractAbstract
[en] In the scenarios for deep, geological nuclear-waste repositories, clayey soils will be hydrated, heated, cooled and dried. The numerical modelling of these mechanical processes is a key issue. Performance assessment of deep repositories for heat-generating radioactive waste would benefit from improvements in mechanical stress-strain constitutive modelling of the coupled thermo-hydro-mechanical behaviour. The presented framework allows progress in understanding the most involved phenomena relevant to nuclear-waste repositories and their coupled nature. It could be used both in the design and in the performance assessment of repositories. It may be applied to disposal in clay formations and to hard-rock repositories where artificially compacted clay is to be used as buffer and backfill. Such a constitutive framework may help in understanding some unexplained or controversial behaviours and in defining experimental programmes to answer key questions. (author)
Primary Subject
Source
Hugi, M. (ed.) (National Cooperative for the Disposal of Radioactive Waste (Nagra), Wettingen (Switzerland)); Bossart, P.; Hayoz, P. (Federal Office of Topography (swisstopo), Wabern (Switzerland)) (eds.); National Cooperative for the Disposal of Radioactive Waste (Nagra), Wettingen (Switzerland); Federal Office of Topography (swisstopo), Wabern (Switzerland). Funding organisation: Federal Office of Topography (swisstopo), Wabern (Switzerland); 91 p; ISBN 978-3-302-40023-5; ; ISSN 1661-9285; ; 2007; p. 33-37; 10 Year Anniversary Workshop of Mont Terri Project; Saint-Ursanne (Switzerland); 16-17 May 2006
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Book
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Conference
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AbstractAbstract
[en] Noble liquid calorimetry is a well proven technology that successfully operated in numerous particle physics detectors (D0, H1, NA48, NA62, ATLAS, …). Its excellent energy resolution, linearity, stability, uniformity and radiation hardness as well as good timing properties make it a very good candidate for future hadron and lepton colliders. Recently, a highly granular noble liquid sampling calorimeter was proposed for a possible FCC-hh experiment. It has been shown that, on top of its intrinsic excellent electromagnetic energy resolution, noble liquid calorimetry can be optimized in terms of granularity to allow for 4D imaging, machine learning and - in combination with the tracker measurements - particle-flow reconstruction. This talk will discuss the ongoing R&D to adapt noble liquid sampling calorimetry for an electromagnetic calorimeter of an FCC-ee experiment with a focus on signal extraction, noise mitigation and cryostat material budget. In addition to that, performance studies realized with the FCCSW full simulation framework will be presented.
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Source
HEPHY - Institut für Hochenergiephysik (Austria); vp; Feb 2022; vp; VCI2022: Vienna Conference on Instrumentalisation; Vienna (Austria); 21-25 Feb 2022; Available in electronic form from: https://indico.cern.ch/event/1044975/contributions/4663743/; Available in electronic form from: https://indico.cern.ch/event/1044975/contributions/?config=0d068a40-df13-42c0-b415-7cf8db16ac6c
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Miscellaneous
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Conference
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Francois, B.; Ledac, A.; Michel, J.; Guibert, M.
CEA, 75 - Paris (France)1984
CEA, 75 - Paris (France)1984
AbstractAbstract
[en] An uranium oxide UO2 powder is prepared and 2 to 12% in weight of gadolinium oxide Gd2O3 is added. Then fuel pellets are roughly fabricated, then sintered in a hydrogen atmosphere containing 0,2 to 5% of water vapor. This process has an application in the field of PWR reactors
[fr]
La presente invention se rapporte a la fabrication de pastilles de combustible nucleaire. On prepare une poudre d'oxyde d'uranium UO2 additionnee de 2 a 12% en poids d'oxyde de gadolium Gd2O3 a partir de laquelle on realise des ebauches de pastilles qui sont frittees dans une atmosphere d'hydrogene contenant 0,2 a 5% en volume de vapeur d'eau. Application aux reacteurs nucleaires a eau sous pressionOriginal Title
Procede de fabrication de pastilles de combustible nucleaire contenant un absorbant neutronique temporaire
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Secondary Subject
Source
25 May 1984; 19 Nov 1982; 15 p; FR PATENT DOCUMENT 2536571/A/; FR PATENT APPLICATION 8219394; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 19 Nov 1982
Record Type
Patent
Country of publication
ACTINIDE COMPOUNDS, CHALCOGENIDES, ENRICHED URANIUM REACTORS, FLUIDS, GADOLINIUM COMPOUNDS, GASES, MATERIALS, NEUTRON ABSORBERS, NUCLEAR POISONS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, RARE EARTH COMPOUNDS, REACTOR MATERIALS, REACTORS, THERMAL REACTORS, URANIUM COMPOUNDS, URANIUM OXIDES, VAPORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
No abstract available
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Journal Article
Journal
International Journal of Nuclear Medicine and Biology; v. 1(1); p. 1-14
Country of publication
BEAMS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHARGED PARTICLE DETECTION, DAYS LIVING RADIOISOTOPES, DISPERSIONS, DOCUMENT TYPES, ELECTROMAGNETIC RADIATION, ELECTRONIC EQUIPMENT, FILTERS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, MEASURING INSTRUMENTS, MINUTES LIVING RADIOISOTOPES, MIXTURES, NUCLEI, ODD-ODD NUCLEI, OPTICAL PROPERTIES, ORGANOLEPTIC PROPERTIES, PHOSPHORUS ISOTOPES, PHYSICAL PROPERTIES, POTASSIUM ISOTOPES, RADIATION DETECTION, RADIATION DETECTORS, RADIATIONS, RADIOISOTOPES, RUBIDIUM ISOTOPES, SCINTILLATION COUNTERS, SECONDS LIVING RADIOISOTOPES, SODIUM ISOTOPES, SOLUTIONS
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AbstractAbstract
[en] The rare earth silicate has the following formula: (Ln1-x-y-zLn'xCeyTbz)9.33 (SiO4)6O2 where Ln and Ln' are different and represent La, Gd, Yb and Lu, x, y and z are chosen with 0< x<1, 0< y<0.05, 0< z<0.05, 0< y + z<0.1 and 0< x + y + z<1. The monocrystal is used as scintillator associated to a photodetector for X and/or gamma rays detection
[fr]
Le silicate de lanthanides repond a la formule: (Ln1-x-y-zLn'xCeyTbz)9.33(SiO4)6O2 dans laquelle Ln et Ln' qui sont differents, representent un element des terres rares choisi parmi La, Gd, Yb et Lu, et x, y et z sont tels que: 0≤x<1 0≤y≤0,05 0≤z≤0,05 0< y + z≤0,1 0< x + y + z<1. Ce monocristal est utilisable comme scintillateur associe a un photodetecteur pour la detection des rayons X et/ou gammaOriginal Title
Monocristaux de silicates de lanthanides utilisables comme scintillateurs pour la detection des rayonnements X et gamma
Source
12 Jan 1990; 6 Jul 1988; 16 p; FR PATENT DOCUMENT 2634028/A/; FR PATENT APPLICATION 8809152; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 6 Jul 1988
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Patent
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Francois, B.; Delmas, R.; Caillat, F.; Lacombe, P.
Australian Atomic Energy Commission Research Establishment, Lucas Heights1975
Australian Atomic Energy Commission Research Establishment, Lucas Heights1975
AbstractAbstract
[en] The microscopic study of uranium dioxide sintered in hydrogen, together with density measurements, shows on the one hand that the large scale appearance of pores trapped at the grain boundaries in the course of sintering has the effect of practically stopping densification, and on the other hand that this particular microstructure is stable over a wide range of time and temperature. (author)
Primary Subject
Source
Jan 1975; 6 p; Translated from the French in J. Nucl. Mater. (1965) v. 15(1) p. 105-110.
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Report
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Kauffmann, Y.; Durand, J.P.; Stora, J.P.; Francois, B.
Annual thermionic conversion specialist conference1971
Annual thermionic conversion specialist conference1971
AbstractAbstract
No abstract available
Primary Subject
Source
p. 330-335; 1971; Inst. of Electrical and Electronics Engineers, Inc; New York; IEEE thermionics conversion specialist conference; San Diego, California, USA; 4 Oct 1971
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Book
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Conference
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AbstractAbstract
[en] A process is described for sintering a powder of metallic oxides particularly UO2, PuO2. The powder is oxidized to obtain on its surface a layer of hydrated oxide of the metal. If the oxides are UO2, PuO2, their mixture or ThO2, the treated powder can be used for nuclear fuel pellet fabrication by cold compression and subsequent sintering
[fr]
L'invention concerne un procede de traitement d'une poudre d'oxyde metallique, en particulier de UO2, PuO2 en vue de son frittage. Ce procede consiste a oxyder ladite poudre de facon a former sur sa surface une couche d'oxyde hydrate du meme metal. Lorsque l'oxyde est UO2, PuO2 et leurs melanges ainsi que ceux prepares avec ThO2, la poudre traitee peut etre utilisee pour la fabrication de pastilles combustibles nucleaires par compression a froid suivie d'un frittageOriginal Title
Procede de traitement d'une poudre d'oxyde metallique et utilisation de la poudre traitee pour la fabrication de pastilles de combustible nucleaire
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Source
21 Oct 1983; 19 Apr 1982; 19 p; FR PATENT DOCUMENT 2525208/A/; FR PATENT APPLICATION 8206677; Available from Institut National de la propriete Industrielle, Paris (France); Application date: 19 Apr 1982
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Patent
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AbstractAbstract
No abstract available
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Technical note.
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Journal Article
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International Journal of Nuclear Medicine and Biology; v. 1(3); p. 147-152
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BETA DETECTION, BIOLOGICAL MATERIALS, BLOOD PLASMA, BLOOD SERUM, BROMINE 82, CALCIUM 47, CHROMIUM 51, COBALT 58, COMPARATIVE EVALUATIONS, COPPER 64, EFFICIENCY, GAMMA SPECTROSCOPY, GOLD 198, INTERNAL CONVERSION RADIOISOTO, IODINE 131, IRON 59, LIQUID SCINTILLATION DETECTORS, LIQUID SCINTILLATORS, NUCLEAR MEDICINE, OPACITY, POTASSIUM 42, RADIOBIOLOGY, SELENIUM 75, SODIUM 22, SODIUM 24, SOLUTIONS, STRONTIUM 85, TECHNETIUM 99, URINE, YTTERBIUM 169
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BETA-PLUS DECAY RADIOISOTOPES, BIOLOGICAL WASTES, BLOOD, BODY FLUIDS, BROMINE ISOTOPES, CALCIUM ISOTOPES, CHARGED PARTICLE DETECTION, CHROMIUM ISOTOPES, COBALT ISOTOPES, COPPER ISOTOPES, DAYS LIVING RADIOISOTOPES, DISPERSIONS, ELECTRON CAPTURE RADIOISOTOPES, EVEN-ODD NUCLEI, GOLD ISOTOPES, HEAVY NUCLEI, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, IRON ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, MEASURING INSTRUMENTS, MEDICINE, MINUTES LIVING RADIOISOTOPES, MIXTURES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, OPTICAL PROPERTIES, PHOSPHORS, PHYSICAL PROPERTIES, POTASSIUM ISOTOPES, RADIATION DETECTION, RADIATION DETECTORS, RADIOISOTOPES, SCINTILLATION COUNTERS, SECONDS LIVING RADIOISOTOPES, SELENIUM ISOTOPES, SODIUM ISOTOPES, SPECTROSCOPY, STRONTIUM ISOTOPES, TECHNETIUM ISOTOPES, WASTES, YEARS LIVING RADIOISOTOPES, YTTERBIUM ISOTOPES
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AbstractAbstract
[en] In the French context, a comparative study is made between PWR line and heavy water line (Candu type). Following criteria have been taken into account: kWh cost, technology, industrial environment required, uranium supply, safety. As a conclusion, the study considers that heavy water line, as it is easy to implement and uranium-saving and because of its good operating results, should be a valuable waiting line before fast breeder reactors implementation
[fr]
Une etude comparative est menee dans le contexte francais entre la filiere PWR et la filiere a eau lourde (type CANDU). Les criteres consideres sont: le cout du kWh, la technologie, l'environnement industriel requis, l'approvisionnement en uranium, la securite. L'etude conclut que la filiere a eau lourde, de par sa simplicite, l'economie d'uranium qu'elle implique et les bons resultats d'exploitation, se revele comme une filiere intermediaire valable en attendant l'arrivee des surregenerateursOriginal Title
Comparaisons entre les filieres a eau pressurisee et a eau lourde
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Journal Article
Journal
Revue de l'Energie; v. 27(282); p. 208-218
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