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The application of the Monte-Carlo neutron transport code MCNP to a small "nuclear battery" system (Universitat Politècnica de CatalunyaUniversity of Manchester, 2009)
Master thesis (pre-Bologna period)
Restricted access - author's decisionThe project consist in calculate the keff to a small nuclear battery. The code Monte- Carlo neutron transport code MCNP is used to calculate the keff. The calculations are done at the beginning of life to know the capacity ...