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
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
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.
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
KEYWORDS: ENDF FORMAT