E. Abonneau, The ASTRID project: status and prospects towards the conceptual design phase, Proc. of ICAPP, pp.447-455, 2014.

J. Rouault, ASTRID, The SFR GENIV Technology Demonstrator Project: Where Are We, Where Do We Stand For, Proc. of ICAPP 2015, Paper 15439, SFEN, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02509083

P. Lo and . Pinto, The Safety orientations during ASTRID conceptual design phase, Proc. of FR13, Paper CN-199-267, IAEA CN-199, 2013.

M. Ladurelle, An original and efficient project organization for ASTRID, Proc. of FR13, Paper CN-199-264, IAEA CN-199, 2013.

J. Rouault, Japan-France Collaboration on the ASTRID Program and Sodium Fast Reactor, Proc. of ICAPP 2015, Paper 15440, SFEN, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02506803

J. W. Collins, Assessing risk and driving risk mitigation for First-Of-A-Kind advanced reactors, Proceedings of the ASME 2011 Small Modular Reactor Symposium, SMR2011, ASME, 2011.

D. C. Crawford, An approach to fuel development and qualification, Journal of Nuclear Materials, vol.371, pp.232-242, 2007.

J. Salotti, Manned missions to Mars: Minimizing risks of failure, Acta Astronautica, vol.93, pp.148-161, 2014.
URL : https://hal.archives-ouvertes.fr/hal-00929697

J. C. Mankins, Technology readiness assessments: A retrospective, Acta Astronautica, vol.65, pp.1216-1223, 2009.

G. Rodriguez, Development of experimental facility platform in support of the ASTRID program, Proc. of FR13, Paper CN-199-122, IAEA CN-199, 2013.

O. Gastaldi, Experimental platforms in support of the ASTRID program: Main experimental needs and devoted existing or planned facilities, Proc. of ICAPP 2015, Paper 15126, SFEN, 2015.

D. Tenchine, Some thermal hydraulic challenges in sodium cooled fast reactors, Nuclear Engineering and Design Journal, vol.240, pp.1195-1217, 2010.

D. Tenchine, International benchmark on the natural convection test in Phénix reactor, Nuclear Engineering and Design Journal, vol.258, pp.189-198, 2013.

D. Tenchine, Status of CATHARE code for sodium cooled fast reactors, Nuclear Engineering and Design Journal, vol.245, pp.140-152, 2012.

D. Tenchine, Status of TRIO U code for sodium cooled fast reactors, Nuclear Engineering and Design Journal, vol.242, pp.307-315, 2012.

D. Tenchine, Gas entrainment issues in sodium cooled fast reactors, Nuclear Engineering and Design Journal, vol.270, pp.302-311, 2014.

H. Kamide, Sodium experiments on natural circulation decay heat removal and 3D simulation of plenum thermal hydraulics, Proc. of FR13, Paper CN-199-137, IAEA CN-199, 2013.

G. Laffont, ASTRID power conversion system based on steam and gas options, Proc. of ICAPP, pp.447-455, 2014.

L. Cachon, Status of the Sodium Gas Heat Exchanger (SGHE) Development for the Nitrogen Power Conversion System Planned for the ASTRID SFR Prototype, Proc. of ICAPP 2015, Paper 15439, SFEN, 2015.
URL : https://hal.archives-ouvertes.fr/cea-02506798