1. NAME AND TITLE

MIXEN: Code System to Replace Files 4 and 6 of ENDF-6 with Files 4 and 5 of ENDF/B-IV

2. CONTRIBUTOR

Institute of Advanced Studies, Brazil.

3. CODING LANGUAGE AND COMPUTER

Fortran IV; CDC Cyber 170/750, IBM RISC 6000.

4. NATURE OF PROBLEM SOLVED

MIXEN replaces files 4 and 6 of the Evaluated Nuclear Data File version 6 (ENDF-6) by files 4 and 5 of ENDF/B-IV. Withe the use of this program, several nuclear data processing systems which were not designed to process the new double-differential data of ENDF-6 can be used to generate multigroup libraries based on the newly evaluated resonance parameters and cross section given in files 2 and 3 of ENDF-6 and the angular distributions given in files 4 and 5 of END/B-IV.

5. METHOD OF SOLUTION

MIXEN requires two ENDF/B versions as input tapes and reads from the terminal screen the material identification numbers (MAT) which will be processed. The program does not update the reaction index.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

The sample problem took about 2 seconds on an IBM RISC 6000 Model 550 under the AIX 3.1 operating system.

8. COMPUTER HARDWARE REQUIREMENTS

The code was developed on the CDC Cyber 170/750 and tested on an IBM RISC 6000.

9. COMPUTER SOFTWARE REQUIREMENTS

The code was written in Fortran V. The IBM XLF compiler version 2.2 was used on the IBM RISC 6000.

10. REFERENCE

Alexandre D. Caldeira. "MIXEN: A Program That Replaces Files 4 and 6 of ENDF-6 By Files 4 and 5 of ENDF/B-IV," Instituto de Estudos Avancados, SAO PAULO, Brasil.

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one DS/HD (1.2 MB) 5.25-in. diskette which include the source files, sample input and output.

12. DATE OF ABSTRACT

June 1992.