Výsledky vyhledávání

Akademický článek

NUWARD SMR safety approach and licensing objectives for international deployment

Autor: Francis, D., Beils, S.

Publikováno v: In Nuclear Engineering and Technology March 2024 56(3):1029-1036

Akademický článek

THE LiCore POWER PLANT SIMULATOR OF THE MOLTEN SALT FAST REACTOR

Autor: Laureau A., Rosier E., Merle E., Beils S., Bruneau O., Blanchon J.C., Gathmann R., Heuer D., Passelaigue F., Vaiana F., Zanini A.

Publikováno v: EPJ Web of Conferences, Vol 247, p 06030 (2021)

Molten salt reactors as liquid-fuelled reactors are flexible in terms of operation or design choices, but they are very different in terms of design, operation and safety approach compared to solid-fuelled reactors. Such reactors call for a new defin

Externí odkaz: https://doaj.org/article/c43a59b0efb74dacbc492b3c0c3fd2cd

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Conference

THE LiCore POWER PLANT SIMULATOR OF THE MOLTEN SALT FAST REACTOR.

Autor: Margulis, M., Blaise, P., Laureau, A., Rosier, E., Merle, E., Beils, S., Bruneau, O., Blanchon, J.C., Gathmann, R., Heuer, D., Passelaigue, F., Vaiana, F., Zanini, A.

Publikováno v: EPJ Web of Conferences; 2021, Vol. 247, p1-8, 8p

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Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project

Autor: Merle, E., Allibert, A., Beils, S., Cammi, A., Carluec, B., Carpignano, A., Delpech, S., Di Ronco, A., Dulla, S., Flauw, Y., Gerardin, D., Gerber, A., Heuer, D., Laureau, A., Lorenzi, S., Massone, M., Rineiski, A., Tiberi, V., Uggenti, A. C.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::648e73981fda9339b8ee66b8f8e9fd37
http://hdl.handle.net/11311/1085516

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Considerations on GEN IV safety goals and how to implement them in future sodium-cooled fast reactors

Autor: Gauthe, P., Guidez, J., Bourgue, L., Beils, S., Carluec, B.

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, Yekaterinburg, Russia

International audience; From a general perspective generation IV (GEN IV) reactors shall excel in safety and, as part of a continuous improvement process, provide safety enhancements. Safety objectives for GEN III reactors are already very ambitious

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::3f56416f7c11b05f98fd9115a3c1ab64
https://hal.science/hal-02419647

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ASTRID project : Main progress on safety design provisions

Autor: Lo Pinto, P., Costes, L., Quellien, P., Carluec, B., Beils, S., Verdier, A., Bourgue, L.

Publikováno v: International Congress on Advances in Nuclear Power Plants (ICAPP-2017)
International Congress on Advances in Nuclear Power Plants (ICAPP-2017), Apr 2017, Tokyo, Japan

International audience; ASTRID is the Advanced Sodium Technological Reactor for Industrial Demonstration which is intended to prepare the Generation IV reactor, with improvements in safety and operability. In order to comply with the related specific

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::4932b5d64ed7bc238b412c0982ce6369
https://hal-cea.archives-ouvertes.fr/cea-02435095

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