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A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors
Bonifetto, R., Dulla, S., Ravetto, P., Richard, L. Savoldi, Zanino, R.Volume:
261
Language:
english
Journal:
Nuclear Engineering and Design
DOI:
10.1016/j.nucengdes.2013.03.030
Date:
August, 2013
File:
PDF, 2.78 MB
english, 2013