Nuclear Reference Data Portal
Look up cross-section libraries by nuclide, browse the periodic table, and copy ready-to-use material cards for MCNP, Serpent, and OpenMC.
Periodic Table
Click any element to see its isotopes, available cross-section libraries, and ZAID identifiers.
Library suffixes — what each is for
MCNP and Serpent use suffixes like .80c, .71c, .20t. Use .XXc for continuous-energy neutron data (thermal through fast). Use .XXt for thermal S(α,β) when modeling bound scatterers (water, graphite, etc.). Use .XXp for photon transport.
Materials Library
Browse 41 pre-built material compositions — fuels, cladding, moderators, shielding, and absorbers — with copy-paste code for all three codes.
Library Reference
Comprehensive table of cross-section library suffixes (.80c, .71c, etc.) with library names, temperatures, energy ranges, and guidance on when to use each.