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Fast-running tool dedicated to power excursion simulations in sodium-cooled fast reactor17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 17), Sep 2017, Xi'An, China. pp.95-108
Conference papers
cea-02434010v1
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Status of severe accident studies at the end of the conceptual design of astrid feedback on mitigation featuresFR 17, Jun 2017, Yekaterinburg, Russia
Conference papers
hal-02419660v1
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Sodium-cooled fast reactor pin model for predicting pin failure during a power excursionNuclear Engineering and Design, 2018, 335, pp.279-290. ⟨10.1016/j.nucengdes.2018.05.023⟩
Journal articles
hal-01851226v1
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Advanced validation methodology for SFR simulation toolsNuclear Engineering and Design, 2019
Journal articles
cea-02340025v1
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