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RSIC CODE PACKAGE PSR-239


1. NAME AND TITLE

RGENDF: Format Translation from NJOY GENDF Format to ENDF/B-V and Other Formats.

2. CONTRIBUTOR

Aerospace Technology Center, Institute of Advanced Studies, Sao Jose dos Campos, Brazil.

3. CODING LANGUAGE AND COMPUTER

Fortran 77; CDC Cyber 170/750.

4. NATURE OF PROBLEM SOLVED

RGENDF is an interface program which reformats GENDF multigroup cross section libraries generated by the GROUPR module of NJOY into ENDF/B-V, EXPANDA, PFCOND and COMPAR formats.

5. METHOD OF SOLUTION

RGENDF reads from the GENDF file and calculates the elastic removal cross-section, absorption cross-section (MF=3, MT=100), and inelastic scattering matrix reactions. Variable JCODE determines the format to be written.

6. RESTRICTIONS OR LIMITATIONS

RGENDF reads "BCD formatted files (MF) 1, 3, 5 and 6." The ENDF/B-V formatted file contains files 1 and 3. Only neutron data is interpreted. More information is included in Appendix A.

7. TYPICAL RUNNING TIME

The following are execution times for the sample problems run on the CDC Cyber 170/750.

JCODE = 1 40.64 seconds

JCODE = 2 12.39 seconds

JCODE = 3 6.53 seconds

JCODE = 4 7.82 seconds

8. COMPUTER HARDWARE REQUIREMENTS

The code runs on the CDC Cyber 170/750.

9. COMPUTER SOFTWARE REQUIREMENTS

The CDC FTN5 compiler is required.

10. REFERENCES

E. S. Chalhoub and Jaime Anaf, "RGENDF - An Interface Program Between the NJOY Code and Codes Using Multigroup Cross Sections," INDC(BZL)-023/GV (Feb. 1988) translated by the IAEA into English from Portuguese IEAv-013/87 (Sept. 1987).

Notes on CDC random-access routines: OPENMS, READMS and WRITMS.

11. CONTENTS OF CODE PACKAGE

Included are the referenced documents and one (360K) DOS diskette containing source code plus sample problem input and output.

12. DATE OF ABSTRACT

March 1989.

KEYWORDS: ENDF/B-V; FORMAT TRANSLATION; NEUTRON