Computational Benchmark for Neutron Penetration in Iron

J. S. Hendricks; L. L. Carter

doi:dx.doi.org/10.13182/NSE81-A21340

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Home / Publications / Journals / Nuclear Science and Engineering / Volume 77 / Number 1

Computational Benchmark for Neutron Penetration in Iron

J. S. Hendricks, L. L. Carter

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 71-83

Technical Paper / dx.doi.org/10.13182/NSE81-A21340

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A calculational benchmark of neutron transport through a slab of iron is based on a rigorous Monte Carlo treatment of ENDF/B-IV and ENDF/B-V cross sections. The model consists of 2-, 14-, and 40-MeV neutrons incident on a 3-m infinite slab. This benchmark problem can be used to validate multigroup cross-section libraries and the associated multigroup transport codes. Plots and tables of the data show the spatial and energy distribution of neutrons for monoenergetic normally incident sources.