Cross-Section Library Reference
MCNP and Serpent use numeric suffixes (e.g. .80c, .71c) to identify cross-section libraries. This page explains the naming convention and lists common libraries with their temperatures and energy ranges.
Suffix naming convention
The suffix format is .XXy where XX is a library identifier and y is the data type.
| Type | Description |
|---|---|
| c | Continuous-energy neutron interaction data. The primary data type for transport calculations. |
| p | Photoatomic interaction data for photon transport (MODE P). |
| t | Thermal scattering S(α,β) data for bound-atom thermal treatment. |
| d | Dosimetry cross sections for activation and dose calculations. |
| u | Unresolved resonance probability tables. |
Library families
ENDF/B — Evaluated Nuclear Data File (US)
NNDC / BNL / LANL
The primary US nuclear data library maintained by the Cross Section Evaluation Working Group (CSEWG). ENDF/B-VIII.0 (2018) is the latest release with significant improvements to light nuclei, actinides, and thermal scattering data.
https://www.nndc.bnl.gov/endf/JEFF — Joint Evaluated Fission and Fusion File (Europe)
NEA Data Bank / OECD
The European evaluated library jointly developed by NEA member countries. JEFF-3.3 (2017) features strong structural material and fission product evaluations, often complementary to ENDF/B.
https://www.oecd-nea.org/dbdata/jeff/JENDL — Japanese Evaluated Nuclear Data Library
JAEA
Japan's comprehensive evaluated library. JENDL-5.0 (2021) includes extensive updates to minor actinides and fission products, particularly strong for fast-reactor applications.
https://wwwndc.jaea.go.jp/jendl/jendl.htmlSuffix table
| Suffix | Library | Temperature | Type | Energy range | Description |
|---|---|---|---|---|---|
| .80c | ENDF/B-VIII.0 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Latest US evaluated library. Recommended for most applications.(recommended) |
| .81c | ENDF/B-VIII.0 | 600 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VIII.0 at 600 K for hot-zero-power conditions. |
| .82c | ENDF/B-VIII.0 | 900 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VIII.0 at 900 K for fuel-temperature conditions. |
| .83c | ENDF/B-VIII.0 | 1200 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VIII.0 at 1200 K for high-temperature fuel. |
| .84c | ENDF/B-VIII.0 | 2500 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VIII.0 at 2500 K for accident-condition fuel temperatures. |
| .71c | ENDF/B-VII.1 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Widely used US library. Default in many MCNP installations.(recommended) |
| .72c | ENDF/B-VII.1 | 600 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VII.1 at 600 K. |
| .73c | ENDF/B-VII.1 | 900 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VII.1 at 900 K. |
| .74c | ENDF/B-VII.1 | 1200 K | Continuous-energy neutron | 1e-11 – 20 MeV | ENDF/B-VII.1 at 1200 K. |
| .70c | ENDF/B-VII.0 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Legacy US library. Superseded by VII.1 and VIII.0. |
| .66c | ENDF/B-VI.8 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Legacy library. Not recommended for new calculations. |
| .84p | ENDF/B-VIII.0 | N/A | Photoatomic | 1 keV – 100 GeV | Photon interaction cross sections (photoelectric, Compton, pair production).(recommended) |
| .70p | ENDF/B-VII.0 | N/A | Photoatomic | 1 keV – 100 GeV | Legacy photon interaction data. |
| .20t | ENDF/B-VIII.0 | 293.6 K | Thermal S(α,β) | < 4 eV | Thermal scattering law for bound atoms. Required for accurate thermal-spectrum transport.(recommended) |
| .21t | ENDF/B-VIII.0 | 350 K | Thermal S(α,β) | < 4 eV | S(α,β) data at 350 K. |
| .22t | ENDF/B-VIII.0 | 400 K | Thermal S(α,β) | < 4 eV | S(α,β) data at 400 K. |
| .23t | ENDF/B-VIII.0 | 500 K | Thermal S(α,β) | < 4 eV | S(α,β) data at 500 K. |
| .24t | ENDF/B-VIII.0 | 600 K | Thermal S(α,β) | < 4 eV | S(α,β) data at 600 K. |
| .25t | ENDF/B-VIII.0 | 800 K | Thermal S(α,β) | < 4 eV | S(α,β) data at 800 K. |
| .10t | ENDF/B-VII.1 | 293.6 K | Thermal S(α,β) | < 4 eV | Thermal scattering law tables from ENDF/B-VII.1. |
| .11t | ENDF/B-VII.1 | 350 K | Thermal S(α,β) | < 4 eV | S(α,β) data from ENDF/B-VII.1 at 350 K. |
| .12t | ENDF/B-VII.1 | 400 K | Thermal S(α,β) | < 4 eV | S(α,β) data from ENDF/B-VII.1 at 400 K. |
| .31c | JEFF-3.1 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | European Joint Evaluated Fission and Fusion File. |
| .32c | JEFF-3.2 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Updated JEFF library with improved actinide evaluations. |
| .33c | JEFF-3.3 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Latest JEFF release. Strong for structural materials and fission products.(recommended) |
| .40j | JENDL-4.0 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Japanese Evaluated Nuclear Data Library. |
| .50j | JENDL-5.0 | 293.6 K | Continuous-energy neutron | 1e-11 – 20 MeV | Latest Japanese library with comprehensive updates to minor actinides.(recommended) |