1. NAME AND TITLE
RESENDD: A Code System for Reconstruction of Resonance Cross Sections from Evaluated
Nuclear Data in ENDF/B Format.
Japan Atomic Energy Research Institute, Tokyo, Japan, through the OECD NEA Data Bank, Gif-sur-Yvette, France.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; CDC CYBER 740 (A) and VAX-11/70 (B).
4. NATURE OF PROBLEM SOLVED
RESENDD is a computer code system for calculating resonance cross sections from evaluated
resonance parameters in the ENDF/B format.
5. METHOD OF SOLUTION
RESENDD is an improvement of RESEND done by modifying the multi-level Breit-Wigner formula, adding a function of Doppler broadening cross sections and of calculating zero-Kelvin cross sections.
RESENDD has the following new functions not available in RESEND: 1) both ENDF/B-IV and ENDF/B-V formats are available for an input file; 2) calculations method of the multi-level Breit-Wigner formula was improved not to take a long CPU time and to permit J-unknown resonances; 3) an energy dependent scattering radius can be treated; 4) resonance parameters for the Reich-Moore formula can be processed; 5) modification of energy selection method was made; 6) option for interpolation in the unresolved resonance region was introduced; 7) distant resonances can be treated approximately.
RESENDD can treat the multilevel Breit-Wigner formula even in the case where J values of
resonances are unknown. The Reich-Moore formula also can be treated. In the case of unresolved
resonance cross section calculation, parameter of cross-section interpolation may be chosen.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for RESENDD.
8. COMPUTER HARDWARE REQUIREMENTS
RESENDD is operable on the CDC CYBER 740 (A) or the VAX-11/780 (B) computers. For
compilation of RESENDD, the AUTODBL (DBLPAD) option is recommended.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
T. Nakagawa, "Program RESENDD (Version 84-07): A Program for Reconstruction of Resonance
Cross Sections from Evaluated Nuclear Data in the ENDF/B Format (Modified Version of RESEND),"
AERI-M 84-192 (September 1984).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and two (1.2MB) DOS diskettes which contain the source
code, cross section library data, and sample problem input.
12. DATE OF ABSTRACT
KEYWORDS: NEUTRON CROSS SECTION PROCESSING; ENDF FORMAT