Open AccessCriticality calculations with MCNP{trademark}: A primer
Author(s) -
Corey Harmon,
R.D. Busch,
J.F. Briesmeister,
R.A. Forster
Publication year - 1994
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/10171469
Subject(s) - criticality , fissile material , computer science , monte carlo method , nuclear engineering , reliability engineering , nuclear physics , physics , engineering , mathematics , neutron , statistics
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