MCNP Monte Carlo: a precis of MCNP

Kenneth J. Adams

doi:10.1117/12.267945

27 February 1997 MCNP Monte Carlo: a precis of MCNP

Kenneth J. Adams

Proceedings Volume 2867, International Conference Neutrons in Research and Industry; (1997) https://doi.org/10.1117/12.267945
Event: Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, 1996, Crete, Greece

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.

Citation Download Citation

Kenneth J. Adams "MCNP Monte Carlo: a precis of MCNP", Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); https://doi.org/10.1117/12.267945

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