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Nuclear data for MCNP

  • Nuclear Data and Monte-Carlo Codes
  • Conference paper
  • First Online:
Monte-Carlo Methods and Applications in Neutronics, Photonics and Statistical Physics

Part of the book series: Lecture Notes in Physics ((LNP,volume 240))

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Abstract

The sources of neutron and photon transport data are described as well as the processing of the evaluated data sets into continuous-energy and multigroup cross-section sets. The procedures for checking and validating the processed data are discussed. The question of why so many data sets are available is addressed by indicating the differences between data sets as well as their relative strengths and weaknesses. Suggestions are made to help the MCNP user in selecting appropriate cross-section sets.

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Authors and Affiliations

  1. Radiation Transport Group Los Alamos National Laboratory, 87545, Los Alamos, New Mexico

    Robert C. Little & Robert E. Seamon

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  1. Robert C. Little
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  2. Robert E. Seamon
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Editor information

Raymond Alcouffe Robert Dautray Arthur Forster Guy Ledanois B. Mercier

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© 1985 Springer-Verlag

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Little, R.C., Seamon, R.E. (1985). Nuclear data for MCNP. In: Alcouffe, R., Dautray, R., Forster, A., Ledanois, G., Mercier, B. (eds) Monte-Carlo Methods and Applications in Neutronics, Photonics and Statistical Physics. Lecture Notes in Physics, vol 240. Springer, Berlin, Heidelberg. https://doi.org/10.1007/BFb0049031

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  • DOI: https://doi.org/10.1007/BFb0049031

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  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-540-16070-0

  • Online ISBN: 978-3-540-39750-2

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