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