1. NAME AND TITLE
MINIGAL: Neutron Cross Section Processing System for Calculating Average Values from
Data in the Standard United Kingdom Nuclear Data Library Format.
Atomic Energy Establishment, Winfrith, Dorchester, Dorset, United Kingdom through the NEA Computer Programme Library, Ispra (Varese), Italy.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; IBM 3033.
4. NATURE OF PROBLEM SOLVED
MINIGAL processes data in one of the standard UK Nuclear Data Library formats.
5. METHOD OF SOLUTION
MINIGAL calculates cross sections at 0.0253 eV and at 14.04 MeV, Maxwellian averages, epithermal integrals, and fission spectrum averages. Input data can be on cards, card image tape, or binary tape. The user may specify the Maxwellian temperature and the energy limits of the regions over which averages are taken or may accept default values.
The thermal average cross sections are given in Westcott's Convention, except for total and elastic
scatter for which simplified Maxwellian averages are used. Epithermal integral cross sections are
conventional resonance integrals except for elastic scatter for which the resonance integral is divided
by the lethargy interval. A fission spectrum of Walt-Cranberg form and mean energy 2.0159 MeV is
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for MINIGAL.
8. COMPUTER HARDWARE REQUIREMENTS
MINIGAL is operable on the IBM 3033 computers.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
J. S. Story, Mrs. V. J. Fry, and R. W. Smith, "The 4-70 Program MINIGAL at AEE Winfrith,"
UNGD(79)/P211 (October 1979).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
code, library data, and sample problem input and output.
12. DATE OF ABSTRACT
KEYWORDS: MULTIGROUP CROSS SECTION PROCESSING; NEUTRON CROSS SECTION PROCESSING