FEDMIX: Neutron transmission functions and lumped averaged cross-sections from standardized evaluated neutron data

Published: 01-12-1989| Version 1 | DOI: 10.17632/m2chwdb654.1
Contributor:
P. Vertes

Description

Abstract The FEDMIX code is used for modeling the neutron transmission and self-indication experiments to be performed on isotope mixture samples. The world-wide accepted evaluated neutron data files (ENDF/B, KEDAK, etc.) can be used as an outgoing data base. The statistics of group-averaged cross-sections and functionals in the unresolved energy region are facilitated and applied to the fitting of average resonance parameters to the poorly resolved experimental data. Title of program: FEDMIX Catalogue Id: ABLF_v1_0 Nature of problem Group-averaged functionals are calculated from evaluted neutron data. The fluctuation error of functionals are calculated in the unresolved energy region and used in the fitting of average resonance parameters to the measured group-averaged cross-sections. Versions of this program held in the CPC repository in Mendeley Data ABLF_v1_0; FEDMIX; 10.1016/0010-4655(89)90020-9 This program has been imported from the CPC Program Library held at Queen's University Belfast (1969-2019)

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