Current status of MCNP6 as a simulation tool useful for space and accelerator applications
Abstract
For the past several years, a major effort has been undertaken at Los Alamos National Laboratory (LANL) to develop the transport code MCNP6, the latest LANL Monte-Carlo transport code representing a merger and improvement of MCNP5 and MCNPX. We emphasize a description of the latest developments of MCNP6 at higher energies to improve its reliability in calculating rare-isotope production, high-energy cumulative particle production, and a gamut of reactions important for space-radiation shielding, cosmic-ray propagation, and accelerator applications. We present several examples of validation and verification of MCNP6 compared to a wide variety of intermediate- and high-energy experimental data on reactions induced by photons, mesons, nucleons, and nuclei at energies from tens of MeV to about 1 TeV/nucleon, and compare to results from other modern simulation tools.
Keywords
Cite
@article{arxiv.1207.5076,
title = {Current status of MCNP6 as a simulation tool useful for space and accelerator applications},
author = {S. G. Mashnik and J. S. Bull and H. G. Hughes and R. E. Prael and A. J. Sierk},
journal= {arXiv preprint arXiv:1207.5076},
year = {2015}
}
Comments
4 pages, 3 figures, Proc. 11th Conference on the Intersections of Particle and Nuclear Physics (CIPANP 2012), St. Petersburg, FL, May 28 - June 3, 2012