Welcome to the official release of the JEFF-4T3 library!
After our initial unofficial release in September 2023, we are thrilled to announce that JEFF-4T3 is now officially available as of February 2024. This release marks a significant milestone in our continuous efforts to provide accurate and reliable nuclear data to the scientific community.
For a comprehensive overview of the changes introduced in JEFF-4T3, we invite you to refer to this spreadsheet: JEFF-4 Evolution. It provides detailed insights into the modifications made.
Kindly be aware that the most recent official release from JEFF continues to be JEFF-3.3.
Fission Yields (FY):
Thermal Scattering Law (TSL):
Neutron induced reaction cross sections evaluations :
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Changes compared to JEFF-4T2.2: - F-19, Si-28, Si-29, Si-30, Fe-56, Cu-63, Cu-65 are from INDEN - Eight-groups delayed neutron data were restored from JEFF-3.3 for Th-227, Th-229, U-232, U-236, Np-238, Pu-242, Am-242m, Am-243, Cf-249, Cf-251 - The gamma decay cascade for inelastic scattering (MF12 and MF14) was completed whenever necessary - B-9 and Be-10 are taken from TENDL-2023, as they were missing in previous versions of JEFF - New evaluations for Ar-36,38, V-51, Xe-124,126,128-132,134,136, Pm-147, Bi-209, U-235,236,238, Np-238, Pu-239,240,241 - All TENDL-2021 files have been replaced with the latest TENDL-2023 data, with the exception of Np-237 - All JENDL-4 files have been replaced with the latest JENDL-5 data - Minor typos and format issues were corrected Kindly be aware that JEFF-4T3.0 Cu-63 and Cu-65 cannot be directly used by TRIPOLI-4. For that reason, the files were corrected and given as a separate patch. For more info about the changes, go to GitLab. For a comprehensive overview of the changes, please refer to the following spreadsheet: JEFF-4 Evolution.
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| Release | Format | Code used | Content | N. Eval. | Download | |
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| JEFF-4T3 | ENDF6 | - | Cu-63 and Cu-65 cross section evaluations for TRIPOLI-4 users | 2 | ||
| JEFF-4T3 | ENDF6 | - | Cross section evaluations (download all) | 567 | ||
| JEFF-4T3 | ENDF6 | - | Cross section evaluations (choose and download) | 567 | ||
| JEFF-4T3 | ACE | NJOY2016.56 | Continuous-energy cross section data | 567 | ||
| JEFF-4T3 | Text | - | XSDIR for MCNP | 1 | ||
| JEFF-4T3 | GENDF-1102 | NJOY2016.56 and PREPRO2021 | Groupwise cross section data | 567 | ||
| JEFF-4T3 | HDF5 | NJOY2016.56 and OPENMC | Continuous-energy cross section data | 567 | ||
| JEFF-4T3 | XML | FUDGE-6.2.0 | Cross section evaluations + covariance data | 967 | ||
| JEFF-4T3 | XML | FUDGE-6.2.0 | List of files for which the FUDGE processing failed | 1 | ||
| JEFF-4T3 | NJOY2016.56 and PREPRO2021 | Plots (choose and download) | 1701 | |||
| JEFF-4T3 | Excel | NEA Pipeline | Status of the pipeline for each isotope | 1 | ||
Last modified: 01 March 2024
