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Manuscript Title: Neutron transmission functions and lumped averaged cross-sections from standardized evaluated neutron data (FEDMIX system).
Authors: P. Vertes
Program title: FEDMIX
Catalogue identifier: ABLF_v1_0
Distribution format: gz
Journal reference: Comput. Phys. Commun. 56(1989)199
Programming language: Fortran.
Computer: EC-1061 (IBM COMPATIBLE).
Operating system: IBM OS.
RAM: 500K words
Word size: 32
Peripherals: magnetic tape.
Keywords: Nuclear physics, Nuclear reaction, Neutron cross-sections, Neutron transmission, General experiments, Group-averaged neutron Cross-sections.
Classification: 17.4, 17.8.

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.

Solution method:
Numerical quadrature of cross-sections given either in tabelled or in parametric form. Generation of stochastic ladders in unresolved resonance region. Statistical evaluation of group-averaged cross- sections. Least-square fitting.


Unusual features:

Running time:
It depends on the representation of neutron data, on the required accuracy, on the width of energy groups and so on.