1. NAME AND TITLE
F5TAB: Code System for Converting Energy Distribution Cross Section Data to Tabulated Data.
Chinese Nuclear Data Center, Beijing, China, through the Organization for Economic and
Development (OECD) Nuclear Data Bank (NEADB), Gif-sur-Yvette, France.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; VAX 11/780.
4. NATURE OF PROBLEM SOLVED
F5TAB converts from energy distribution data format (in ENDF/B-IV, file 5) with various types
of laws to tabulated data points in linear-linear interpolation form.
5. METHOD OF SOLUTION
F5TAB 1) converts the function parameters to tabulated data with sufficient energy points, 2) uses linearization, 3) adds zero-value points at the ends of the energy region, 4) does normalization.
Only ENDF file 5 is used; other files are copied onto the output file.
F5TAB may be useful for re-normalization of ENDF/B-IV file 5, which should already be in linear
tabulated data form, if some of the data has been changed.
6. RESTRICTIONS OR LIMITATIONS
The input data file must be correctly coded in ENDF/B-IV format, especially file 5.
7. TYPICAL RUNNING TIME
4.2 seconds are required for the test problem on the VAX. In general, execution times depend on
the size of the input data file.
8. COMPUTER HARDWARE REQUIREMENTS
F5TAB is operable on the VAX 11/780 computer. It uses less than 200 K-bytes.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran 77 compiler is required. The subroutines LINTAB and THIN are standard for general
usage on linearization and normalization.
L. X. Shen, "Program F5TAB - Version 84-12," Informal Notes (December 1984).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (360KB) DOS diskette which contains the source
code and sample problem input.
12. DATE OF ABSTRACT
KEYWORDS: ENDF FORMAT; NEUTRON CROSS SECTION PROCESSING