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
The French Prototype of 4th Generation Reactor: ASTRID", Proceedings of Annual meeting on nuclear technology, 2011. ,
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
Progress in the design of the ASTRID nuclear island", Proceedings, 2018. ,
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
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
Seismic isolation system in civil work design of Gen IV nuclear power plant buildings", Proceedings, 2018. ,
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
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
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