Nucleide

MCNP I/O

Parse MCNP material cards, xsdir, meshtal, MCTAL, and WWINP files.

The mcnp-io crate reads and writes several MCNP-family file formats. On this page we can only work from text strings, which is still enough to inspect decks and convert small files.

Supported formats

  • Material cards — m1 92235 -0.04 92238 -0.96 style definitions, including comment metadata.
  • xsdir — cross-section directory with AWR table and continuous-energy entries.
  • meshtal — fmesh tally output with structured mesh results and relative errors.
  • MCTAL — header, standard tally bodies (f/d/u/s/m/c/e/t bins plus vals pairs), and kcode cycles.
  • WWINP — Cartesian weight-window lower bounds.

Try it

Select a parser and paste a file snippet. The demo returns a JSON summary that you can inspect without leaving the page. For meshtal files, load the sample and view the tally as a z-slice heatmap; parsed xsdir tables are summarised as a histogram by element, with companion views of table counts by library suffix and the AWR distribution. For MCTAL files, load the sample to see the header plus a per-tally table of pair counts and totals.

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See also