MCNP - a general Monte Carlo code for neutron and photon transport
作者： R. A. Forster , T. N. K. Godfrey
DOI: 10.1007/BFB0049033
关键词:
摘要: MCNP is a very general Monte Carlo neutron-photon transport code with approximately 250 person years of Group X-6 development invested. It highly portable, user-oriented, and true production as it used about 60 Cray hours per month by 150 Los Alamos users. has its data base the best cross-section evaluations available. contains state-of-the-art traditional adaptive techniques to be applied solution an ever-increasing number problems. Excellent user-oriented documentation available for all facets code. Many useful important variants exist special applications.
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