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 — ZAIDs and suffix guidance also apply to SCONE ACE inputs.

118 elements182 nuclides41 materials

Periodic Table

Click any element to see its isotopes, available cross-section libraries, and ZAID identifiers (MCNP, Serpent, SCONE ACE).

La–Lu
Ac–Lr
Nonmetal
Halogen
Noble Gas
Alkali Metal
Alkaline Earth Metal
Transition Metal
Post-Transition Metal
Metalloid
Lanthanide
Actinide
Unknown

Library suffixes — what each is for

MCNP and Serpent use suffixes like .80c, .71c, .20t; SCONE ACE libraries embed the same nuclide naming — your nuclearData.materials ZAID indices must match tables in the ACE file you load. 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.

.80cENDF/B-VIII.0 · 293.6 K · Neutron
.71cENDF/B-VII.1 · 293.6 K · Neutron
.33cJEFF-3.3 · 293.6 K · Neutron
.50jJENDL-5.0 · 293.6 K · Neutron
.20tENDF/B-VIII.0 · 293.6 K · Thermal S(α,β)
Full library reference →

Materials Library

Browse 41 pre-built material compositions — fuels, cladding, moderators, shielding, and absorbers — with copy-paste code for MCNP, Serpent, and OpenMC; compositions map to SCONE nuclearData with your ACE suffixes.

Browse Materials Library

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.

Browse Library Reference

Engineering Calculators

Atom ↔ Weight Fraction Converter

Enter element symbols (e.g. U, O) or Z numbers and their fractions. Results update in real time.

NuclideAtom Frac

Number Density Calculator

N = ρ · NA / M · f  —  convert mass density to number density.

Presets:

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ReactorMC Community Library

A shared database where nuclear engineers upload, tag, and discuss reactor input files — benchmarks, teaching models, and production decks for every Monte Carlo code.

Share your models

Upload MCNP, OpenMC, Serpent, or SCONE input files with descriptions, tags, and reactor metadata.

Review and discuss

Comment on models, suggest improvements, and rate community contributions — more eyes, fewer errors.

Search and reuse

Find the reactor you need — PWR pin cells, BWR assemblies, full-core BEAVRS — and start editing instead of building from scratch.

Open the Community Library

Common Lookups

Uranium →Plutonium →Zirconium →Iron →UO₂ (4.5%) →Light Water →SS316 →B₄C →