Search Results - "Sudreau, F."

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

“…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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Tribological qualification of cobalt-free coatings for pressurized water reactor primary-circuit gate valve applications by Cachon, L., Denape, J., Sudreau, F., Lelait, L.

“…The object of this study is to qualify cobalt-free alternative alloys for valve applications. This paper focuses on tribological characterizations of numerous…”
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A refined statistical approach to thermal fatigue life prediction by SUDREAU, F, OLAGNON, C, FANTOZZI, G, LECLERCQ, O

“…Finding new applications for ceramic materials requires a better knowledge of thermal fatigue behavior. However, result-scattering inherent to thermal fatigue…”
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Viscosity models for corium melts by Ramacciotti, Muriel, Journeau, Christophe, Sudreau, François, Cognet, Gérard

“…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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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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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

“…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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REFINED STATISTICAL APPROACH TO THERMAL FATIGUE LIFE PREDICTION by Sudreau, F, Olagnon, C, Fantozzi, G, Leclercq, O

“…Result-scattering inherent to thermal fatigue and duration of a thermal fatigue cycle lead to a lack of experimental results. A new approach has been developed…”
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