Aug 30, 2024 · ENDF/B-VIII.0 fully incorporates the new Neutron Data Standards, includes improved thermal neutron scattering data and uses new evaluated data from the Coordinated …

The U.S.'s Evaluated Nuclear Data File (ENDF) is the default low energy nuclear data library in particle transport codes such as MCNP, SCALE and even GEANT4.

Data stored in the ENDF-6 format are difficult to understand. The interpretted ENDF, developed by R. MacFarlane in Los Alamos, translates ENDF-6 data into human readable format.

The ENDF/B-VIII.1 release is the newest evaluated nuclear data library produced, distributed, and recommended by CSEWG for use in nuclear science and technology applications.

The NNDC is responsible for assigning ENDF reference numbers for all formal laboratory reports associated with the ENDF system.

Download ENDF/B-VIII.0 Full ENDF/B-VIII.0 Library [488 Mb Zip file] [Format Manual] Download checksums:

It contains thermal scattering-law data, largely supplied by LANL, with the addition of SiO 2 in ENDF/B-VII.1 from ORNL. The neutron cross section standards sublibrary was carried over …

• Interactive access to ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B-VI.8 libraries. • Neutron cross section distributions (MF=3). • Experimental data in EXFOR format.

The ENDF library project is run by the Cross Section Evaluation Group, beginning in 1966 and has produced seven major and numerous minor library releases since.

Twenty-four materials and reactions are available in ENDF-V format containing covariance files. The Department of Energy put restrictions on the distribution of the library for the first time.