1. NAME AND TITLE

FDMXPC: Code System for Calculation of Neutron Transmission and Other Functionals from Evaluated Data in ENDF Format.

2. CONTRIBUTOR

Central Research Institute of Physics, Institute of Atomic Energy Research, Budapest, Hungary.

3. CODING LANGUAGE AND COMPUTER/OPERATING SYSTEM

Fortran-77; PCAT; PC-386; PC-486.

4. NATURE OF PROBLEM SOLVED

FDMXPC processes evaluated neutron cross-section data in ENDF format to group-averaged functionals mainly for the modelling of neutron transmission experiments. It is also possible to treat mixtures of isotopes. This release of the code has been extended to use ENDF-6 format.

5. METHOD OF SOLUTION

Breit-Wigner, Reich-Moore or Adler-Adler neutron cross-section formula are integrated numerically over specified energy intervals by means of Romberg's integration method.

6. RESTRICTIONS OR LIMITATIONS

None.

7. TYPICAL RUNNING TIME

Very different, depending upon the problem specification.

8. COMPUTER HARDWARE REQUIREMENTS

Personal computer minimum AT with 286 processor, math coprocessor is recommended.

9. COMPUTER SOFTWARE REQUIREMENTS

Minimum: DOS 4.0, Microsoft Fortran compiler 5.0, or any other equivalent system or compiler.

10. REFERENCES

P. Vertes, "FDMXPC README."

P. Vertes, "Calculation of Transmission and Other Functionals from Evaluated Data in ENDF Format by Means of Personal Computers," KFKI-1991-10/G (1991).

P. Vertes, "Processing of Evaluated Neutron Data Files in ENDF Format on Personal Computers," Informal Notes (1991).

11. CONTENTS OF CODE PACKAGE

Included in the package are the referenced documents and 1 DS/HD disk which includes the source files, test case input data and output.

12. DATE OF ABSTRACT

September 1992.