Utilizing the burnup capability in MCNPX to perform...

Utilizing the burnup capability in MCNPX to perform depletion analysis of an MNSR fuel

Boafo, E.K., Alhassan, E., Akaho, E.H.K.
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Volume:
73
Language:
english
Journal:
Annals of Nuclear Energy
DOI:
10.1016/j.anucene.2014.07.030
Date:
November, 2014
File:
PDF, 744 KB
english, 2014
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