Publicado 4 números por año
ISSN Imprimir: 0276-1459
ISSN En Línea: 1943-6181
Indexed in
MATERIAL EFFECTS ON MULTIPHASE PHENOMENA IN LATE PHASES OF SEVERE ACCIDENTS OF NUCLEAR REACTORS
SINOPSIS
This paper reviews and presents work carried out in the French Atomic Energy Commission (CEA) on the subject of nuclear severe accidents, i.e. those which are accompanied by melting of the nuclear core material. The emphasis is on the (crucial) thermodynamic and material behaviour of corium melts in the solidus-liquidus temperature interval, which is linked to the thermal hydraulic description. A global model approach is proposed. The work is presented in the context of the overall international effort in the area.
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Seiler Jean Marie, Ratel Gilles, Combeau Hervé, Gaus-Liu Xiaoyang, Kretzschmar Frank, Miassoedov Alexei, Transient refractory material dissolution by a volumetrically-heated melt, Nuclear Engineering and Design, 280, 2014. Crossref
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Spindler Bertrand, Tourniaire Bruno, Seiler Jean-Marie, Simulation of MCCI with the TOLBIAC-ICB code based on the phase segregation model, Nuclear Engineering and Design, 236, 19-21, 2006. Crossref
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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, Ex-vessel core melt stabilization research (ECOSTAR), Nuclear Engineering and Design, 221, 1-3, 2003. Crossref
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Combeau H., Appolaire B., Seiler J.M., Interface temperature between solid and liquid corium in severe accident situations: A comprehensive study of characteristic time delay needed for reaching liquidus temperature, Nuclear Engineering and Design, 240, 8, 2010. Crossref
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Guillaumé Mathieu, Combeau Hervé, Seiler Jean-Marie, An improved interface model for molten corium–concrete interaction, Nuclear Engineering and Design, 239, 6, 2009. Crossref
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Late Containment Failure, in Nuclear Safety in Light Water Reactors, 2012. Crossref
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FUKASAWA Masanori, TAMURA Shigeyuki, SAITO Masaki, Analysis of B4C Influences on Thermodynamic Properties and Phase Separation of Molten Corium with Ionic Liquid U-Zr-Fe-O-B-C-FPs Database, Journal of Nuclear Science and Technology, 46, 7, 2009. Crossref
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In-Vessel Core Degradation, in Nuclear Safety in Light Water Reactors, 2012. Crossref
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Pham Quynh Trang, Seiler Jean Marie, Combeau Hervé, Gaus-Liu Xiaoyang, Kretzschmar Frank, Miassoedov Alexei, Modeling of heat transfer and solidification in LIVE L3A experiment, International Journal of Heat and Mass Transfer, 58, 1-2, 2013. Crossref
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Pham Q.T., Seiler J.M., Combeau H., Heat & mass transfer and interface temperature during simulated melt-concrete interaction with composition variation in ARTEMIS 2D experiment, Nuclear Engineering and Design, 318, 2017. Crossref
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Tourniaire B., Varo O., Assessment of Two-Phase Flow Heat Transfer Correlations for Molten Core-Concrete Interaction Study, Nuclear Technology, 164, 1, 2008. Crossref
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Amblard Michel, Delhaye Jean-Marc, Froment Karine, Seiler Jean-Marie, Tourniaire Bruno, Consequences of Different Types of Contact Between Water and Molten Steel: The ANAIS Experiments, Nuclear Technology, 153, 3, 2006. Crossref
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Seiler J.M., Jamet S., TIM model application to corium concrete interaction: Ablation regimes and instabilities, Nuclear Engineering and Design, 352, 2019. Crossref
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Journeau Christophe, Piluso Pascal, Molten Core Concrete Interaction, in Comprehensive Nuclear Materials, 2020. Crossref
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Amidu Muritala Alade, Olatubosun Samuel Abiodun, Ayodeji Abiodun, Addad Yacine, Severe accident in high-power light water reactors: Mitigating strategies, assessment methods and research opportunities, Progress in Nuclear Energy, 143, 2022. Crossref
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Froment K., Seiler J. M., Poirier J., Colombel L., Determining Cooling Screen Slagging Reactor Operating Temperature, Energy & Fuels, 29, 8, 2015. Crossref
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Nandan Shambhavi, Fichot Florian, Duval Fabien, A two-phase mathematical model to describe the dissolution of corium crust by molten steel, Nuclear Engineering and Design, 375, 2021. Crossref
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Fichot F., Michel B., Almjashev V., Le Guennic C., Bakouta N., Le Tellier R., Piluso P., Keim T., Chemical Interactions of Molten Steel with (U-Zr-O) Corium: Main Outcomes of the CORDEB Program, Nuclear Engineering and Design, 388, 2022. Crossref
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Skobe Tomaž, Leskovar Matjaž, Influence of corium composition on ex-vessel steam explosion, Annals of Nuclear Energy, 133, 2019. Crossref