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Nuclear Technology Volume 181, 2013 - Issue 2
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Technical Paper

Methodology for Designing a Sodium-Cooled Fast Reactor with Inherent Safety

N. E. StauffCEA, DEN, DER, 13108 Saint Paul-lez-Durance, France
,
L. BuironCEA, DEN, DER, 13108 Saint Paul-lez-Durance, France
,
B. FontaineCEA, DEN, DER, 13108 Saint Paul-lez-Durance, France
&
G. RimpaultCEA, DEN, DER, 13108 Saint Paul-lez-Durance, France
Pages 241-250 | Published online: 22 Mar 2017

References

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  • G. Rimpault et al., “The ERANOS Code and Data System for Fast Reactor Neutronic Analyses,” Proc. Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002), Seoul, Korea, October 7-10, 2002, American Nuclear Society (2002).
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  • N. E. Stauff, “Multicriteria Methodology to Design a Sodium-Cooled Carbide-Fueled GEN-IV Reactor,” PhD Thesis, Orsay University (2011).

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