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An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor
Aufiero, M., Cammi, A., Fiorina, C., Leppänen, J., Luzzi, L., Ricotti, M.E.Volume:
441
Language:
english
Journal:
Journal of Nuclear Materials
DOI:
10.1016/j.jnucmat.2013.06.026
Date:
October, 2013
File:
PDF, 3.46 MB
english, 2013