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.

2. CONTRIBUTOR

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 used.

6. RESTRICTIONS OR LIMITATIONS

None noted.

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.

10. REFERENCE

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

April 1984.