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Advantages of mesh tallying in MCNP5 for soil analysis calculations

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Abstract

The Monte Carlo code, MCNP5, includes a mesh and lattice tally option useful for large matrix calculations. Recently, a fast lattice tally (FLT) was developed for MCNPX. We used these two codes to model an in-situ soil analysis system based on inelastic neutron scattering. The tallies were utilized to calculate the reaction rates of fast neutrons with carbon via inelastic reactions. The results of these three tallies and their respective computational times are compared, and the advantages of these methodologies discussed.

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References

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Authors and Affiliations

  1. The University of Texas at Austin, 1 University Station, Austin, TX, 78759, USA

    O. Doron & S. Biegalski

  2. Environmental Sciences Department, Brookhaven National Laboratory, Bldg. 490D, Upton, NY, 11973, USA

    L. Wielopolski

Authors
  1. O. Doron
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  2. L. Wielopolski
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  3. S. Biegalski
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Correspondence to L. Wielopolski.

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Doron, O., Wielopolski, L. & Biegalski, S. Advantages of mesh tallying in MCNP5 for soil analysis calculations. J Radioanal Nucl Chem 276, 183–186 (2008). https://doi.org/10.1007/s10967-007-0430-8

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  • DOI: https://doi.org/10.1007/s10967-007-0430-8

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