GRUCON - evaluated data processing code package

Purpose

The major objective of GRUCON code package is ENDF data processing for preparing data for various tasks and applications.

Corresponding Author:
Valentin Sinitsa (sinitsa_vv@nrcki.ru)

Content

GRUCON code package (IPPE-NRCKI, 1980-2021) is a system of modules for evaluated nuclear data processing for production of detailed and multi-group working libraries for transport calculations in reactor physics and radiation shielding applications. The package has an original architecture and command language (see INDC-CCP-344). This page presents GRUCON-D: version 2021.12 (certificate of state registration No. 2014663246).

Functions

• read evaluated data files in the ENDF format;
• reconstruct point-wise cross sections from resonance parameters for given temperatures;
• reconstruct point-wise probability tables from average resonance parameters;
• compute cross sections moments in the unresolved resonance range;
• prepare subgroup parameters from cross section moments by Pade technique;
• prepare probability tables in group intervals from point-wise cross sections;
• compute correlation matrices between subgroup cross sections of different reactions, temperatures, materials, successive collisions in slow-down process (generalized subgroups);
• reconstruct Legendre coefficients from resonance parameters with smoothing for given temperatures;
• calculate energy-angular distributions of neutrons scattered on nuclei in free gas and resonance scattering models;
• calculate energy-angular distributions of neutrons scattered on bound nuclei in thermal energy range;
• prepare photon and particle production cross sections;
• prepare radioactive nyclide production cross sections;
• average integral cross sections with build-in or calculated weight function in groups and prepare shielded group cross sections;
• prepare neutron group transition, neutron production in fission, photon or particle production matrices in neutron reactions;
• prepare microscopic group vectors and matrices for mixtures from vectors amd matrices of separated isotopes;
• prepare group matrices for thermal and resonance neutron scattering with upscatter transitions;
• prepare group matrices of photon/particle production in neutron reactions;
• prepare group cross sections and intergroup transition matrices for photo-atomic interactions;
• perform visualized comparison of data files in the PENDF, GENDF, ENDF and GNDS formats, obtained by NJOY, PREPRO and FUDGE processing code systems, with verification purposes;
• output point-wise data in the ACE format for fast/thermal/photo-atomic&atomic-relaxation data for Monte-Carlo transport calculation codes;
• output group-wise data in the BNAB, MATXS, CCCC and TEMBR formats for neutron-photon transport calculation codes;

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