Three sets of software packages are presented on the UKRNDC site: the PREPRO-2015 package for ENDF/B pre-processing, the package AUX-2015 for input preparation and the FILTER software package.

The PREPRO-2015 program package (the package name comes from the English "pre-processing") began to be created by D. Cullin (University of California, Livermore, USA) in 1974 and continues to be constantly updated in parallel with updating the presentation format in evaluated nuclear data libraries (ENDL). The modern software package PREPRO-2015 consists of 17 computer codes, which are codes of free access (they can be downloaded from the site https://www-nds.iaea.org/public/endf/prepro/). The PREPRO-2015 software package is intended to convert ENDF/B formatted nuclear data from ENDL to a kind of nuclear-physical quantities, which can then be used for calculations of engineering tasks, as well as for the visualization of nuclear data.

On this site only 5 PREPRO-2015 codes are presented: LINEAR, RECENT, SIGMA1, GROUPIE and MIXER. In choosing these codes, we used the following criteria: 1) the selected codes are obligatory for the calculation of neutron cross sections from the data presented in ENDL; 2) nuclear-physical quantities, calculated with the use of selected codes, make it possible to conduct simple engineering calculations; 3) the selected codes are close analogues of the software modules used in the world-known software complex NJOY, therefore their learning can be considered as the first step to studying this complex.

LINEAR - this program is designed to convert ENDF/B file 3, 23 and 27 data to linear interpolable form. Any section that is already linear-linear interpolable will be thinned.

RECENT - this program is designed to reconstruct the resonance contribution to the cross section in linearly interpolable form, add in any linearly interpolable background cross section and output the result in the ENDF/B format. The cross sections output by this program will be linearly interpolable over the entire energy range.

SIGMA1 - this program is designed to Doppler broaden neutron induced cross sections. Each section of cross sections (file 3) is read from the ENDF/B format. The data is doppler broadened, thinned and output in the ENDF/B format.

GROUPIE - this program is designed to calculate any combination of the following quantities from linearly interpolable tabulated cross sections in the ENDF/B format: 1) unshielded group averaged cross sections; 2) Bondarenko self-shielded group averaged cross sections; 3) multi-band parameters.

MIXER - this program is designed to calculate the energy dependent cross section for a composite mixture of up to 10 different materials.