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A new experimental R&D program associated with the corium jet impingement on the ASTRID core catcher sacrificial material

Autor: Payot, F., Journeau, C., Suteau, C., Serre, F., michel Gradeck, Rimbert, N., Lecoanet, A., Miassoedov, A.

Publikováno v: Scopus-Elsevier
International Congress on Advances in Nuclear Power Plants (ICAPP 18)
International Congress on Advances in Nuclear Power Plants (ICAPP 18), Apr 2018, Charlotte, United States

The strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postulated severe accident relies on the presence of dedicated corium discharge tubes between the active core region and the lower plenum and an in-vessel

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::057a32c9cea4156ec6c67cfe7b7b008a

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Plinius-2 a new corium facility and programs to support the safety demonstration of the astrid mitigation provisions under severe accident conditions

Autor: Serre, F., Payot, F., Suteau, C., Christophe Journeau, Aufore, L., Aletto, T. D., Abonneau, E.

Publikováno v: International Conference on Fast Reactors and Related Fuel Cycles Next Generation Nuclear Systems for Sustainable Development (FR17)
International Conference on Fast Reactors and Related Fuel Cycles Next Generation Nuclear Systems for Sustainable Development (FR17), Jun 2017, Iekaterinbourg, Russia
HAL

International audience; The ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demonstration) is a technological demonstrator of sodium-cooled fast reactor (SFR) designed by the CEA with its industrial partners, with very high level

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::44e659b9e42fd9cf0b398ce05a038a8c
https://hal.archives-ouvertes.fr/hal-02419645

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Improvements in simulation tools to be developed within the framework of the ASTRID project

Autor: Gaillard-Groleas, G., Garnier, J.-C., Hamy, J.-M., Girardi, E., Hirata, M., Grouiller, J.-P., Martin, Lilian, Serre, F., Phelip, M., Doderlein, C., Michel, B., Lainet, M., Fontaine, B., Suteau, C., Gerschenfeld, A., Cardolaccia, J.

Publikováno v: ICAPP 2016-International Congress on Advances in Nuclear Power Plants
ICAPP 2016-International Congress on Advances in Nuclear Power Plants, Apr 2016, San Francisco, United States

International audience; The ASTRID design comprises innovative features compared to past designs. The simulation tools being very important to support the ASTRID design option selection and to assist a robust Safety demonstration, the CEA and its ind

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::f05ceb70eb0922b5c95e414f892a666d
https://hal-cea.archives-ouvertes.fr/cea-02509775

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R&D and Experimental Programs to support the ASTRID Core Assessment in Severe Accidents Conditions

Autor: Serre, F., Payot, F., Suteau, C., Trotignon, L., Batyrbekov, E., Vurim, A., Pakhnits, A., Vityuk, V., Kubo, S., Katoh, A., Tobita, Y., Kamiyama, K., Matsuba, K., Toyooka, J.

Publikováno v: ICAPP 2016-2016 International Congress on Advances in Nuclear Power Plants
ICAPP 2016-2016 International Congress on Advances in Nuclear Power Plants, Apr 2016, San Franscisco, United States

International audience; The ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demonstration) is a technological prototype designed by the CEA with its industrial partners, with very high levels of requirements. Innovative options h

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::a570bb4eae322b50a2970b2d121840e8
https://hal-cea.archives-ouvertes.fr/cea-02509785

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