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Validation of the MCNP5 computer code

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Abstract

The MCNP5 computer code with the ENDF/B6 neutron data library is validated for problems which are of current importance at the Russian Federal Nuclear Center — All-Russia Research Institute of Technical Physics. Comparative calculations performed with the MCNP5 code and its preceding version MCNP4c are identical within the limits of computational error. This confirms that the MCNP5 code can be used instead of the previous versions.

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Authors and Affiliations

  1. Russian Federal Nuclear Center — All-Russia Research Institute of Technical Physics, Russia

    E. N. Lipilina, V. D. Lyutov & É. Ya. Filippova

Authors
  1. E. N. Lipilina
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  2. V. D. Lyutov
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  3. É. Ya. Filippova
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Translated from Atomnaya Énergiya, Vol. 101, No. 2, pp. 112–116, August, 2006.

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Lipilina, E.N., Lyutov, V.D. & Filippova, É.Y. Validation of the MCNP5 computer code. At Energy 101, 564–568 (2006). https://doi.org/10.1007/s10512-006-0131-3

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  • DOI: https://doi.org/10.1007/s10512-006-0131-3

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