Status of severe accident studies at the end of the conceptual design of ASTRID: Feedback on mitigation features

Autor: Bertrand, F., Marie, N., Bachrata, A., Brun-Magaud, V., Droin, J.B., Manchon, X., Herbreteau, K., Farges, B., Carluec, B., Poumerouly, S., Lemasson, D.

Publikováno v: In Nuclear Engineering and Design January 2018 326:55-64

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

Autor: Manchon, X., Bertrand, F., Marie, N., Lance, M., Schmitt, D.

Publikováno v: In Nuclear Engineering and Design October 2017 322:522-535

Simplified thermohydraulic criteria for a comparison of the accidental behaviour of GEN IV nuclear reactors and of PWRs

Autor: Bertrand, F, Marie, N., Bachrata, A., Droin, J.-B., Manchon, X.

Publikováno v: NURETH 18-The 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulic
NURETH 18-The 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Aug 2019, Portland, United States

International audience; A comparison of 3 Generation IV reactor concepts between them and with a PWR of 2nd generation is presented in this paper. The 3 Gen IV reactor concepts considered have been studied at CEA and are briefly presented in the firs

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::881ef8f596e7619e04bcecd6db20c5a0
https://hal-cea.archives-ouvertes.fr/cea-02614127/document

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