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Cited article:

Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations

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Annals of Nuclear Energy 128 69 (2019)
https://doi.org/10.1016/j.anucene.2018.12.037

A neutronics study for improving the safety and performance parameters of a 3600MWth Sodium-cooled Fast Reactor

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Annals of Nuclear Energy 53 464 (2013)
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On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors

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Annals of Nuclear Energy 38 (5) 921 (2011)
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A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors

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Annals of Nuclear Energy 38 (1) 1 (2011)
https://doi.org/10.1016/j.anucene.2010.08.009