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Malet, J.C.; Duverger de Cuy, G.
Proceedings of the CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities. Volume I1983
Proceedings of the CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities. Volume I1983
AbstractAbstract
[en] FLAMME is a computer program designed to calculate the thermodynamic consequences of a kerosene fire in a ventilated or unventilated room. It is a multizone model that describes the exchanges of energy due to thermal radiation and the exchanges of matter due to pyrolysis, to air entrainment by the hot plume, and to the ventilation system
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Los Alamos National Lab., NM (USA); p. 169-181; Oct 1983; p. 169-181; CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities; Los Alamos, NM (USA); 25-28 Apr 1983; Available from NTIS, PC A14/MF A01; 1 as TI84003976
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BUTYL PHOSPHATES, CHEMICAL REACTIONS, ENERGY SOURCES, ENERGY TRANSFER, ESTERS, FOSSIL FUELS, FUELS, HYDROGEN COMPOUNDS, INORGANIC ACIDS, KINETICS, MATHEMATICAL MODELS, NITROGEN COMPOUNDS, NUCLEAR FACILITIES, ORGANIC COMPOUNDS, ORGANIC PHOSPHORUS COMPOUNDS, OXIDATION, OXYGEN COMPOUNDS, PETROLEUM PRODUCTS, PHOSPHORIC ACID ESTERS, REACTION KINETICS
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Malet, J.C.; Duverger de Cuy, G.; Gasteiger, R.; Janberg, K.
Proceedings of the CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities. Volume II1983
Proceedings of the CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities. Volume II1983
AbstractAbstract
[en] Pool fire tests were carried out to simulate certain types of fire liable to occur in fuel reprocessing plants with TBP-kerosene mixtures in quantities ranging from 2nd to 250 liters, with combustion areas fo 78 cm2 to 5 m2. Test results showed that a solvent pool can be ignited at temperatures below the flashpoint by propagation from a localized hot spot in case of very strong local energy input. The transfer coefficients from the mixture to the air and the very high efficiency filters were measured for cesium and thorium, used to simulate the plutonium that could be present in the solvent
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Los Alamos National Lab., NM (USA); p. 391-404; Oct 1983; p. 391-404; CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities; Los Alamos, NM (USA); 25-28 Apr 1983; Available from NTIS, PC A12/MF A01; 1 as TI84003977
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ACTINIDES, ALKALI METALS, BUTYL PHOSPHATES, CHEMICAL REACTIONS, ELEMENTS, ENERGY SOURCES, ESTERS, FLUID FLOW, FLUIDS, FOSSIL FUELS, FUELS, GASES, METALS, NONMETALS, NUCLEAR FACILITIES, ORGANIC COMPOUNDS, ORGANIC PHOSPHORUS COMPOUNDS, OXIDATION, PETROLEUM PRODUCTS, PHOSPHORIC ACID ESTERS, TRANSURANIUM ELEMENTS
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Duverger de Cuy, G.; Miachon, G.; Regnier, J.
CEA, 75-Paris (France)1986
CEA, 75-Paris (France)1986
AbstractAbstract
[en] On the wall of the structure to be cut is fixed a hollow section defining with the wall a duct in which is introduced an inflatable tube bearing the explosive rope. Before firing the tube is inflated and the explosive rope is closely applied on the wall. Application is made to dismantling of radioactive containers, enclosure etc... minimizing the time of exposure to radiations for the personnel
[fr]
On fixe sur la paroi de la structure a decouper un profile definissant avec celle-ci une glissiere dans laquelle on introduit un tube souple gonflable, ce dernier presentant un logement pour le cordeau detonant; avant de proceder a la mise a feu, on gonfle le tube, ce qui a pour effet d'appliquer le cordeau sur la paroi. Application au demantelement d'installations hors d'usage, notamment en milieu dangereuxOriginal Title
Procede et dispositif pour le decoupage d'une structure mince a l'aide d'un cordeau detonant de decoupe
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8 Aug 1986; 5 Feb 1985; 11 p; FR PATENT DOCUMENT 2576825/A/; FR PATENT APPLICATION 85 01564; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 5 Feb 1985
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Patent
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Malet, J.C.; Duverger de Cuy, G.; Casselman, C.; Charpenel, J.; Natta, M.; Devillers, C.
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Services de Recherches de Surete1979
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Services de Recherches de Surete1979
AbstractAbstract
[en] This paper describes the sodium fire programs undertaken by the CEA's Nuclear Safety Department. Experimental results concerning sodium ignition and combustion, sodium fire suppression, sodium aerosol filtration and sodium-concrete contact reactions are given and the applications of these results in the Super-Phenix reactor is discussed
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Aug 1979; 10 p; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979
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[en] FEUNA is a computer code developed to calculate the thermodynamic effects of a sodium fire in a ventilated or unventilated containment volume. Developed jointly by the CEA/DSN and Novatome, the FEUNA code involves two oxide formation reactions, aerosol generation and deposits, heat transfer by convection, conduction and radiation, gas inflow and outflow through the ventilation system and the relief valves. The code was validated by comparing calculated values with the results of an actual sodium fire in a 400m3 caisson. (author)
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International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 259 p; Mar 1979; p. 76-80; IAEA-IWGFR specialists' meeting on sodium fires and prevention; Cadarache (France); 20-24 Nov 1987; 2 refs, 2 figs
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AbstractAbstract
[en] In the scope of the sodium aerosol trapping research effort by the CEA/DSN, the retention capacity and yield were measured for very high efficiency fiberglass filters and several types of prefilters (cyclone agglomerator, fabric prefilters, water scrubbers). (author)
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International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 259 p; Mar 1979; p. 192-198; IAEA-IWGFR specialists' meeting on sodium fires and prevention; Cadarache (France); 20-24 Nov 1987; 7 figs, 1 tab
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Guirlet, J.; Duverger de Cuy, G.; Salle, R.
Treatment of Airborne Radioactive Wastes. Proceedings of a Symposium on Operating and Developmental Experience in the Treatment of Airborne Radioactive Wastes1968
Treatment of Airborne Radioactive Wastes. Proceedings of a Symposium on Operating and Developmental Experience in the Treatment of Airborne Radioactive Wastes1968
AbstractAbstract
[en] The fission products present in nuclear installations create a potential hazard of environmental contamination against which precautions must be taken this is, specifically, the purpose of purification equipment. The first problem is to define the containment and its leakage rate. The efficiency of purification on the off-gas system must be adapted to the hazard and the choice will be guided by the characteristics of the site, in particular the weather conditions and the doses regarded as acceptable for the surrounding population. Purification systems will accordingly vary depending on the type of installation in which they are to be used (reactors, factories, laboratories). This paper describes the different possibilities and shows that systems which are both effective and adaptable can be built. It considers durability of equipment properties and also the additional hazards entailed in handling purification equipment and the accidents which could result from its use. The financial aspects of the different solutions are also discussed. (author)
[fr]
Les produits de fission présents dans les installations nucléaires créent un risque potentiel de contamination de l'environnement contre lequel il faut se prémunir; c’est en particulier le rôle des dispositifs d’épuration. Il s’agit tout d’abord de définir le confinement et son taux de fuite. Sur le dispositif de rejet prévu, l’efficacité de l'épuration doit être adaptée au risque. Les critères du choix sont imposes par les caractéristiques du site, en particulier par les conditions météorologiques et par les doses que l'on peut admettre pour la population environnante. Dans ces conditions, les systèmes d'épuration seront différents suivant les types d'installations (piles, usines, laboratoires). On décrit les différents cas possibles en montrant quedes systèmes souples et efficaces peuvent être réalisés. La permanence des propriétés des dispositifs est examinée, ainsi que les risques supplémentaires entraînés par la manutention et les accidents d’utilisation des dispositifs d’épuration; l'aspect économique des solutions spécifiques est également abordé. (author)Original Title
Conception et Realisation des Systemes d'Epuration de l'Air dans les Installations Nucleaires Francaises
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International Atomic Energy Agency, Vienna (Austria); United States Atomic Energy Commission, Germantown, MD (United States); Harvard University, Cambridge, MA (United States); 835 p; Dec 1968; p. 669-682; Symposium on Operating and Developmental Experience in the Treatment of Airborne Radioactive Wastes; New York, NY (United States); 26-30 Aug 1968; IAEA-SM--110/9; ISSN 0074-1884; ; 8 refs., 4 figs.
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AbstractAbstract
[en] After a sodium leak in a locale, producing a fire, the operator's first concern is to repair the plant. Since the residual sodium and the products of combustion are chemically aggressive, the personnel will have to perform this operation in a hostile environment. This paper presents answers which can be given to the three questions which will however rise: When can the intervention begin? How will it be performed? What should be done with the residues of combustion? This document aims at presenting the different solutions to this problem, these solutions being derived from experiments carried out in France either in the Esmeralda Programme, which is managed jointly by CEA and ENEA, or in the other French programmes. As a general rule, the intervention inside the locale can be made much more easier if: it was foreseen right from the beginning of the design (access under the pipes, anchorage for handling, etc.); the incident can have been localised thanks to the monitoring of locales, enabling the video recording of the first instants, that is, as long as visibility does not fall to zero due to the aerosols from the fire. (author)
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Kozlov, F.A.; Kuznetsova, R.I. (eds.); International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); Physics and Power Engineering Institute, Obninsk (USSR); 342 p; 1989; p. 244-247; IAEA-IWGFR specialists' meeting on sodium fires; Obninsk (USSR); 6-9 Jun 1988
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AbstractAbstract
[en] The studies made in France on magnesium combustion and extinguishing means are associated at the nuclear fuel of the graphite-gas reactor. Safety studies are made for ameliorate our knowledge on: - magnesium combustion - magnesium fire propagation - magnesium fire extinguishing
[fr]
Les etudes menees en France sur la combustion du magnesium et les moyens d'extinction associes sont lies au retraitement des combustibles de la filiere graphite-gaz. Des etudes de surete ont ete lancees pour ameliorer nos connaissances dans les domaines de: - la combustion du magnesium, - la propagation d'un feu de magnesium, - l'extinction d'un feu de magnesiumOriginal Title
Combustion et extinction des feux de magnesium
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Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France); CEA, 75 - Paris (France); 524 p; 1988; p. 207.1-207.13; Societe Francaise d'Energie Nucleaire; Paris (France); LIMET'88: 4. International Conference on Liquid Metal Engineering and Technology; Avignon (France); 17-21 Oct 1988
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Malet, J.C.; Duverger de Cuy, G.; Casselman, C.; Charpenel, J.; Natta, M.; Devillers, C.
International meeting on fast reactor safety technology1979
International meeting on fast reactor safety technology1979
AbstractAbstract
[en] Sodium fire programs undertaken by the CEA's Nuclear Safety Department are described. Experimental results concerning sodium ignition and combustion, sodium fire suppression, sodium aerosol filtration and sodium-concrete contact reactions are given and the application of these results in the Super-Phenix reactor is discussed. 3 refs
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Anon; p. 1192-1200; 1979; p. 1192-1200; American Nuclear Society; LaGrange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979
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