Search Results - "Cognet, G"

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  1. 1

    Physico-chemical analyses and solidification path reconstruction of multi-component oxidic spread melts by Journeau, C, Sudreau, F, Magne, S, Cognet, G

    “…In the case of a hypothetical severe core melt accident in a nuclear power plant, scenarios in which a mixture of core materials could melt and mix with the…”
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    Journal Article
  2. 2

    Corium viscosity modelling above liquidus temperature by Sudreau, F., Cognet, G.

    Published in Nuclear engineering and design (01-12-1997)
    “…In the event of a highly unlikely core melt-down accident in Pressurized Water Reactors (PWR), scenarios in which the reactor pressure vessel fails and the…”
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    Journal Article
  3. 3

    Corium spreading and coolability: CSC Project by Cognet, G, Alsmeyer, H, Tromm, W, Magallon, D, Wittmaack, R, Sehgal, B.R, Widmann, W, De Cecco, L, Ocelli, R, Azarian, G, Pineau, D, Spindler, B, Fieg, G, Werle, H, Journeau, C, Cranga, M, Laffont, G

    Published in Nuclear engineering and design (01-11-2001)
    “…In the context of severe accidents, large R&D efforts throughout the world are currently directed towards ex-vessel corium behaviour. Among the mitigation…”
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    Journal Article Conference Proceeding
  4. 4

    Study of Taylor-Couette flow using a three-segment electrodiffusion probe by SOBOLIK, V, BENABES, B, COGNET, G

    “…The axial and azimuthal components of the shear rate on the wall of the outer fixed cylinder of a pair of concentric cylinders with the inner cylinder rotating…”
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    Journal Article
  5. 5

    Ex-vessel core melt stabilization research (ECOSTAR) by Steinwarz, W, Koller, W, Dyllong, N, Häfner, W, Journeau, C, Seiler, J.M, Froment, K, Cognet, G, Goldstein, S, Fischer, M, Hellmann, S, Nie, M, Eddi, M, Alsmeyer, H, Allelein, H.-J, Spengler, C, Bürger, M, Sehgal, B.R, Koch, M.K, Büscher, T, Alkan, Z, Petrov, J.B, Gaune-Escard, M, Weiss, F.-P, Altstadt, E, Bandini, G

    Published in Nuclear engineering and design (01-04-2003)
    “…The project ECOSTAR (acronym for ex-vessel core melt stabilization research) involves in total 17 organizations from five European countries. The objective of…”
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    Journal Article
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    Study of mass transfer enhancement on liquid/liquid interface by flow instabilities using gallium liquid electrode by Cognet, G., Martemyanov, S.

    Published in Russian journal of electrochemistry (01-04-2008)
    “…Abstrac Using liquid gallium electrodes it was proved that electrodiffusion method is a convenient tool for measuring the mass transfer at liquid/liquid…”
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    Journal Article
  8. 8

    Viscosity models for corium melts by Ramacciotti, Muriel, Journeau, Christophe, Sudreau, François, Cognet, Gérard

    Published in Nuclear engineering and design (01-02-2001)
    “…When a solid phase is in equilibrium with a liquid (partial crystalization), additional information is necessary to estimate the rheological behaviour of such…”
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    Journal Article Conference Proceeding
  9. 9

    Ex-vessel corium spreading: results from the VULCANO spreading tests by Journeau, Christophe, Boccaccio, Eric, Brayer, Claude, Cognet, Gérard, Haquet, Jean-François, Jégou, Claude, Piluso, Pascal, Monerris, José

    Published in Nuclear engineering and design (01-07-2003)
    “…In the hypothetical case of a nuclear reactor severe accident, the reactor core could melt and form a mixture, called corium, of highly refractory oxides (UO…”
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    Journal Article
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    Thermal, physico-chemical and rheological boundary layers in multi-component oxidic melt spreads by Journeau, Christophe, Sudreau, François, Gatt, Jean-Marie, Cognet, Gérard

    “…In the unlikely case of a severe accident in a nuclear reactor, the core material could melt and form a molten mixture named corium. The CEA has undertaken a…”
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    Journal Article
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    Utilization of a transferred arc-plasma rotating furnace to melt and found oxide mixtures at around 2000 degrees C (presentation of the film VULCANO) by Cognet, G, Laffont, G, Jegou, C, Pierre, J, Journeau, C, Sudreau, F, Roubaud, A

    Published in Annales pharmaceutiques françaises (01-03-1999)
    “…Unless security measures are taken, a hypothetical accident resulting from the loss of the cooling circuit in a pressurized water nuclear reactor could cause…”
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    Journal Article
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