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Simplified criteria for a comparison of the accidental behaviour of Gen IV nuclear reactors and of PWRS

Autor: X. Manchon, A. Bachrata, Elsa Merle, T. Le Meute, Nathalie Marie, D. Heuer, Frédéric Bertrand, Jean-Baptiste Droin

Publikováno v: Nucl.Eng.Des.
Nucl.Eng.Des., 2021, 372, pp.110962. ⟨10.1016/j.nucengdes.2020.110962⟩
Nuclear Engineering and Design
Nuclear Engineering and Design, 2021, 372, pp.110962. ⟨10.1016/j.nucengdes.2020.110962⟩

International audience; A cross-comparison of four Generation IV reactor concepts and a PWR of 2nd generation is presented in this paper. 4 Gen IV reactor concepts are considered and are briefly presented in the first part of the paper: SFR of 1500 M

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::00f4a9987161dcb15125e5adc60cb3ec
https://hal.archives-ouvertes.fr/hal-03136705

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Coupled thermalhydraulic-neutronic stability extended criterion in a SFR core

Autor: Frédéric Bertrand, Jean-Baptiste Droin, P. Sciora, X. Manchon, D. Schmitt, Nathalie Marie, Michael J. Lance

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2019, 355, pp.110319. ⟨10.1016/j.nucengdes.2019.110319⟩
Nuclear Engineering and Design, 2019, 355, pp.110319. ⟨10.1016/j.nucengdes.2019.110319⟩

A coupled thermalhydraulic-neutronic extended criterion developed in order to assess the conditions of static instability of the sodium flow in a SFR core during the beginning of an unprotected loss of flow (ULOF) is presented in the first part of th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b3e05d4da49e9de9c9652e836ffff5c8
https://hal.archives-ouvertes.fr/hal-02481998

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Status of severe accident studies at the end of the conceptual design of astrid feedback on mitigation features

Autor: Frédéric Bertrand, X. Manchon, Jean-Baptiste Droin, A. Bachrata, Bernard Carluec, B. Farges, V. Brun-Magaud, D. Lemasson, K. Herbreteau, Nathalie Marie, S. Poumerouly

Publikováno v: FR 17
FR 17, Jun 2017, Yekaterinburg, Russia

International audience; The ASTRID reactor developed by the CEA with its industrial partners, will be used for demonstration of the safety and operability, at the industrial scale, of sodium fast reactors of the 4th generation. Among the goals assign

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0aa1f6a8a55921ccbee3d25cacd187d5
https://hal.archives-ouvertes.fr/hal-02419660/file/201700000425.pdf

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Modeling and analysis of molten fuel vaporization and expansion for a sodium fast reactor severe accident

Autor: X. Manchon, F. Bertrand, D. Schmitt, Nathalie Marie, Michael J. Lance

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, 2017, 322, pp.522-535. ⟨10.1016/j.nucengdes.2017.07.010⟩
Nuclear Engineering and Design, Elsevier, 2017, 322, pp.522-535. ⟨10.1016/j.nucengdes.2017.07.010⟩

International audience; The safety assessment of Sodium-cooled Fast Reactors (SFR) requires to account for hypothetical severe accidents involving the melting down of the core materials. This paper deals with the modeling of a fuel vaporization trans

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::16108b9755b6c381bd04ae9a8b89e9d3
https://cea.hal.science/cea-02418711/document

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