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Chatoux, J.
Australian Atomic Energy Commission Research Establishment, Lucas Heights1975
Australian Atomic Energy Commission Research Establishment, Lucas Heights1975
AbstractAbstract
[en] A discussion is given of a number of problems that arose during the various stages of design and construction which could be divided into two main categories: 1) technical administrative and organisational problems which involved the personnel, 2) purely technical problems. (R.L.)
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Jun 1975; 21 p; 3 figs.; translated from the French in Bull. Inf. Sci. Tech. (no.78), p. 15-21 (Dec 1963); bound with the original.
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AbstractAbstract
No abstract available
Original Title
Fuite d'eau de la piscine principale du reacteur SILOE
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Mar 1987; 3 p; Published in summary form only.
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Report
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AbstractAbstract
[en] After almost 34 year of operation the experimental reactor Siloe is scheduled to close down definitively at the end of 1997. The irradiation programme on the whole is to be transferred to the Osiris reactor in Saclay. The irradiation devices will be installed during 1998. (A.C.)
Original Title
Reacteurs siloe passe le relais
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Journal Article
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Defis du CEA; ISSN 1163-619X; ; (no.63); p. 24-25
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AbstractAbstract
[en] The mechanical properties of the primary wall in a fusion nuclear reactor was investigated through the exposure of stainless steel samples to a neutronic flux equivalent to that real flux which the primary wall is usually exposed to. This neutronic flux was made possible from the fission nuclear reactor SILOE. However, for duplicating closely the behaviour of the primary wall in fusion nuclear reactor, it is suggested that the irradiated sample should be linked with a special apparatus that contains fissionable material such as 235U. Moreover, pre-irradiation time interval should always be employed
Original Title
Convenient methodology for investigating the mechanical properties of the fusion nuclear reactor primary wall
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Source
A summary of a DEA report submitted under the title ''Optimisation d'une irradiation d'acier dans SILOE representative des domages produits dans la premiere paroi d'un reacteur a fusion.'' Universite Scientifique et Medical de Grenoble, 1985.
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Journal Article
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Aalam Al-Zarra; CODEN AAALE; (no.1); p. 82-85
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Royer, J.C.; Moulin, V.; Thomas, Ph.
CEA, Grenoble (France)
Research Facilities for the Future of Nuclear Energy1996
CEA, Grenoble (France)
Research Facilities for the Future of Nuclear Energy1996
AbstractAbstract
[en] Within the scope of improving operation of the SILOE research reactor at the CEA/Grenoble, the SILOE Reactor Department has developed the ALEXIS system. The objectives of this system are to consolidate the knowledge in the operating field and to assist operators for the control of the reactor. A methodology has been developed in order to manage the knowledge related to SILOE. A reference model of the installation contains information, necessary during the development phase of the system. ALEXIS implements all the functionalities required to provide assistance to the operators
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Ait Abderrahim, H. (ed.); Centre d'Etude de l'Energie Nucleaire, Mol (Belgium); 557 p; 1996; p. 252-260; Research Facilities for the Future of Nuclear Energy; Brussels (Belgium); 4-6 Jun 1996; Available from World Scientific Publishing Co. Pte. Ltd., P O Box 128, Farrer Road, Singapore 912805
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Book
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Conference
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AbstractAbstract
[en] To study the behaviour of defective nuclear fuel under irradiation, the service of the studies about the behaviour of nuclear fuels makes areal research work applied in the Siloe reactor. this ability to evaluate the physical phenomenons on the fuels, to analyze them before and after irradiation is a rare wealth and for certain techniques, unrivaled in Europe. (N.C.)
Original Title
Un comportement au-dessus de tout soupcon
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Journal Article
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Bruet, M.; Michel, F.; Perdreau, R.
Dosimetry methods for fuels, cladding, and structural materials1977
Dosimetry methods for fuels, cladding, and structural materials1977
AbstractAbstract
[en] Three experimental methods of determining the fission power in a fuel pin, during irradiation in the SILOE Research Reactor, have been compared: (1) Radial heat conduction is determined by the measurement of the temperature gradient through fuel cladding, (2) In pile gamma scanning, and (3) Incident neutron flux is monitored by self powered detectors, and calculations of the fission rates have been made by using computer code APOLLO (a one dimensional transport code). The methods are briefly described. The results are in agreement within 6%. This intercomparison is of interest due to the fact that those methods would be used at different steps of the irradiation: previsioning, monitoring, and post irradiation examinations
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Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; p. 333-351; 1977; p. 333-351; 2. ASTM-EURATOM symposium on reactor dosimetry: dosimetry methods for fuels, cladding and structural materials; Palo Alto, CA, USA; 2 - 7 Oct 1977
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Report
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Royer, J.C.; Moulin, V.; Monge, F.
CEA Centre d'Etudes de Grenoble, 38 (France). Direction des Reacteurs Nucleaires1995
CEA Centre d'Etudes de Grenoble, 38 (France). Direction des Reacteurs Nucleaires1995
AbstractAbstract
[en] The Service of the Reactor Siloe (CEA/DRN/DRE/SRS), fully aware of the abilities and knowledge of his teams in the field of research reactor operating, has undertaken a project of knowledge engineering in this domain. The following aims have been defined: knowledge capitalization for the installation in order to insure its perenniality and valorization, elaboration of a project for the aid of the reactor operators. This article deals with the different actions by the SRS to reach the aims: realization of a technical model for the operation of the Siloe reactor, development of a knowledge-based system for the aid for operating. These actions based on a knowledge engineering methodology, SAGACE, and using industrial tools will lead to an amelioration of the security and the operating of the Siloe reactor. (authors). 13 refs., 7 figs
Original Title
Modelisation systeme pour l'aide a l'exploitation du reacteur de recherche Siloe
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1995; 11 p; Conference on the intelligent systems in firms; Conference sur les systemes intelligents dans les Entreprises; Montpellier (France); 26-30 Jun 1995
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Report
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Delcroix, V.; Jeanne, G.; Mitault, G.; Schulhof, P.
CEA Grenoble, 38 (France)1964
CEA Grenoble, 38 (France)1964
AbstractAbstract
[en] Siloette is the Siloe mock-up. The main installations are described: various tanks, building, auxiliaries, control systems... Precis ions are given about precautions taken for using spent fuel elements. (authors)
[fr]
Siloette est le modele nucleaire de SILOE. On decrit ses diverses installations: bassins, batiments, auxiliaires, controle... Des precisions sont donnees sur les precautions prises pour y utiliser des elements uses. (auteurs)Original Title
Siloette, modele nucleaire de siloe
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1964; 108 p; 8 refs.
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Report
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AbstractAbstract
No abstract available
Original Title
Instrumentierte Bestrahlungskapsel VADIA zur Messung von Huellrohraufweitungen
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1 fig.; 2 refs. Short communication only.
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Journal Article
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Atomwirtsch., Atomtech; v. 19(7); p. 359-360
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