J. P. Grouiller, Plutonium recycling capabilities of ASTRID reactor, Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, 2017.
URL : https://hal.archives-ouvertes.fr/cea-02435076

F. Gauche, The French Prototype of 4th Generation Reactor: ASTRID", Proceedings of Annual meeting on nuclear technology, 2011.

F. Chanteclair, ASTRID reactor -Design overview and main innovative options for Basic Design, Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, pp.245-400, 2017.
URL : https://hal.archives-ouvertes.fr/cea-02435077

. Ms and . Chenaud, Progress in the design of the ASTRID nuclear island", Proceedings, 2018.

D. Plancq, Progress in ASTRID Sodium Gas Heat Exchanger Development, Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, 2017.
URL : https://hal.archives-ouvertes.fr/hal-02419663

F. Dechelette, The fuel handling route of ASTRID at the beginning of the basic design, Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, 2017.
URL : https://hal.archives-ouvertes.fr/cea-02435094

P. Saunier, Seismic isolation system in civil work design of Gen IV nuclear power plant buildings", Proceedings, 2018.

P. Amphoux, Status of ASTRID architecture in starting of Basic Design phase, Proceedings of ICAPP 2017, p.90408, 2017.
URL : https://hal.archives-ouvertes.fr/cea-02435092

F. Varaine, The Collaboration of Japan and France on the design of ASTRID Sodium Fast Reactor, Proceedings of ICAPP 2017, p.90428, 2017.
URL : https://hal.archives-ouvertes.fr/hal-02419667

F. Varaine, The significant collaboration of Japan and France on the design of ASTRID Sodium Fast Reactor since, Proceedings of GIF Symposium, pp.16-17, 2014.
URL : https://hal.archives-ouvertes.fr/cea-02328977