IAEA0848: RECENT2007, Reconstruction of Cross Sections Data from Resonance Parameters

Program-name Package-ID Status RECENT IAEA0848/01 Obsolete RECENT IAEA0848/02 Obsolete RECENT-82.1 IAEA0848/03 Obsolete RECENT-83.2 IAEA0848/04 Obsolete RECENT-86.1 IAEA0848/05 Obsolete RECENT-86.2 IAEA0848/06 Obsolete RECENT-87.1 IAEA0848/07 Obsolete RECENT-87.1 IAEA0848/08 Obsolete RECENT-89.1 IAEA0848/09 Obsolete RECENT-92.1 IAEA0848/10 Obsolete RECENT-94.1 IAEA0848/11 Obsolete RECENT-94.2 IAEA0848/12 Obsolete RECENT-96.1 IAEA0848/13 Obsolete RECENT2000 IAEA0848/14 Obsolete RECENT2002 IAEA0848/15 Obsolete RECENT2004 IAEA0848/16 Obsolete RECENT2007 IAEA0848/17 Tested

Machines used: Package-ID Orig.Computer Test Computer IAEA0848/17 Many Computers Linux-based PC,PC Windows

3. DESCRIPTION OF PROBLEM OR FUNCTION - RECENT reconstructs energy- dependent neutron total elastic, capture, and fission cross sections from a combination of resonance parameters and tabulated background cross sections. RECENT uses the linearly interpolable form of cross sections and resonance parameters. The cross section output is linearly interpolable over the entire energy range. Entire calculations, not just cross sections, are output in the result file, which is in ENDF/B format. The output includes the original resonance parameters in a form that can be used in Doppler broadening and self-shielding calculations.

IAEA0848/17:

This version include the updates up to JANUARY 30, 2007.
Changes in ENDF/B-VII Format and procedures, as well as the evaluations themselves, make it impossible for versions of the ENDF/B pre-processing codes earlier than PREPRO 2007 (2007 Version) to accurately process current ENDF/B-VII evaluations.
The present code can handle all existing ENDF/B-VI evaluations through release 8, which will be the last release of ENDF/B-VI.

MODIFICATIONS FROM PREVIOUS VERSIONS:
-------------------------------------
Recent VERS. 2007-1 (JAN. 2007):
- checked against all ENDF/B-VII;
- decoupled page size from max. # of resonances; increased page size from 120,000 to 750,000 data points;
- kept max. # of resonance at 120,000;
- corrected all background = 0 case

4. METHOD OF SOLUTION - Resonance parameters may be represented using any combination of the representations allowed in ENDF/B:
(1) Resolved data
    a) single-level Breit-Wigner
    b) multi-level Breit-Wigner
    c) Adler-Adler
    d) Reich-Moore
    e) hybrid. R-functions.
(2) Unresolved data
    a) all parameters constant or energy independent
    b) fission parameters energy dependent
    c) all parameters energy dependent.
RECENT starts by calculating the cross sections at the energies corresponding to the peak of each resonance, as well as a fixed number of half-widths on each side of each resonance. Starting from this basic grid of points the program will continue to halve each interval until the cross sections for all reactions at the center of the interval can be defined by linear interpolation from the ends of the interval to within the user specified accuracy criteria. All resonances are treated exactly.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - RECENT uses only the ENDF/B BCD format, not binary and can handle data in any version of the ENDF/B format (I through VI). In order to be combined with the resonance contribution, the background cross sections must be given at temperature 0K and must be linearly interpolable. If these conditions are not met, the background cross section will be ignored and only the resonance contribution will be output.

6. TYPICAL RUNNING TIME - A few seconds.

7. UNUSUAL FEATURES OF THE PROGRAM - The Edit mode provides an inexpensive method of determining the type of resonance parameters used by any given set of parameters. In this mode the user can also determine the amount of common core allocation necessary to carry out the resonance reconstruction. - The allowable error may be energy independent or energy dependent. It is described with a tabulated function of up to 20 (energy,error) pairs. - The backward thinning minimizes the number of data points output for each reaction.

10. REFERENCES -
IAEA0848/17:
- IAEA Nuclear Data Section:
PREPRO2007, 2007 ENDF/B Pre-processing Codes (ENDF/B-VII Tested)
IAEA-NDS-39, Rev. 13, March 17, 2007

11. MACHINE REQUIREMENTS - The package is designed to be used with many machines. Make files for almost all kind of computers are included.

12. PROGRAMMING LANGUAGE(S) USED -
IAEA0848/17: FORTRAN-77

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - Several OS can be used.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHOR -
Nuclear Data Section
IAEA
P.O. Box 100
A-1400 VIENNA
AUSTRIA

16. MATERIAL AVAILABLE -
IAEA0848/17:
General description of the PrePro2007 programs
Documentation
Compressed files for MAC, Readme file for MAC
Author's Make file for PCLinux, Author's LINUX executable
Author's PCWindows compile batch
Author's PCWindows executable
Fortran source files for different platfor
UNIX Makefiles for different platforms
Author's VMS executable, Author's compile command file

17. CATEGORIES -

- A. Cross Section and Resonance Integral Calculations

Keywords: BREIT-WIGNER FORMULA, CROSS SECTIONS, ENDF/B, PROCESSING, RESOLVED REGION, RESONANCE INTEGRALS, UNRESOLVED REGION