Výsledky vyhledávání - "Stephane Picchi"

Oxidation during fuel-coolant interaction Advances and modeling

Autor: Olivia Coindreau, M. Hadj-Achour, Stephane Picchi, V. Loisel, J. A. Zambaux, Renaud Meignen

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2019, 346, pp.200-208. ⟨10.1016/j.nucengdes.2019.02.008⟩

International audience; Following the OECD SERENA phase 2 program and EC SARNET-2 network conclusions, oxidation was identified as a major issue for a comprehensive modelling of Fuel Coolant Interaction (FCI). Indeed, the topic is very complex, invol

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6bf82efc46e72835eda0d262f1ebd6f9
https://hal.archives-ouvertes.fr/hal-02524205/document

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The challenge of modeling fuel–coolant interaction: Part II – Steam explosion

Autor: Renaud Meignen, Stephane Picchi, Julien Lamome, Bruno Raverdy

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2014, 280, pp.528-541. ⟨10.1016/j.nucengdes.2014.08.028⟩

International audience; In the course of a severe accident in a nuclear power plant cooled or moderated by water, the core might melt and flow down into the water. Under certain circumstances, a steam explosion might develop during the mixing of the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::50770946b337109c144443dfe8cfcaf4
https://doi.org/10.1016/j.nucengdes.2014.08.028

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The challenge of modeling fuel–coolant interaction: Part I – Premixing

Autor: Sebastian Castrillon Escobar, Julien Lamome, Stephane Picchi, Bruno Raverdy, Renaud Meignen, Gregory Nicaise

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2014, 280, pp.511-527. ⟨10.1016/j.nucengdes.2014.08.029⟩

International audience; Fuel-coolant interaction is a complex mixing process that can occur during the course of a severe accident in a nuclear power plant involving core melting and relocation. Under certain circumstances, a steam explosion might de

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f62002ed971e6101c28ea817fa7fe516
https://doi.org/10.1016/j.nucengdes.2014.08.029

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Capabilities of MC3D to investigate the coolability of corium debris beds

Autor: Renaud Meignen, Stephane Picchi, Bruno Raverdy, Tanguy Janin, L. Piar

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2017, 319, pp.48-60. ⟨10.1016/j.nucengdes.2017.04.005⟩

International audience; A nuclear severe accident progression may lead to the formation of a corium debris bed either in the vessel lower head (in-vessel debris bed) or in the vessel pit (ex-vessel debris bed). For safety analyses it is essential to

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bad75fbd42f403ccde4d1fe974ac3f9c
https://hal.archives-ouvertes.fr/hal-02553384

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