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Proceedings Paper

MCNP Monte Carlo: a precis of MCNP
Author(s): Kenneth J. Adams
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Paper Abstract

MCNP is a general purpose 3D time-dependent neutron, photon, and electron transport code.It is highly portable and user- oriented, and backed by stringent software quality assurance practices and extensive experimental benchmarks. The cross section database is based upon the best evaluations available. MCNP incorporates state-of-the-art analog and adaptive Monte Carlo techniques. The code is documented in a 600 page manual which is augmented by numerous Los Alamos technical reports which detail various aspects of the code. MCNP represents over a megahour of development and refinement over the past 50 year and an ongoing commitment to excellence.

Paper Details

Date Published: 27 February 1997
PDF: 10 pages
Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267945
Show Author Affiliations
Kenneth J. Adams, Los Alamos National Lab. (United States)

Published in SPIE Proceedings Vol. 2867:
International Conference Neutrons in Research and Industry
George Vourvopoulos, Editor(s)

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