1. NAME AND TITLE

WIMS-ANL, Version 4.00: Deterministic Code System for Lattice Calculation.
 

2. CONTRIBUTOR

Argonne National Laboratory, Argonne, IL.
 

3. CODING LANGUAGE AND COMPUTER

Fortran 77; Unix Sun and PC (Windows 95, 98, NT and Linux) (C00698MNYCP00).
 

4. NATURE OF PROBLEM SOLVED

The WIMS-ANL code is an extension of the Winfrith WIMS-D4 code for lattice cell computations. This code has been tailored to address some of the problem areas encountered in dealing with research reactor fuels, experiment, reflector and control regions. The SUPERCELL option eliminates some of the limitations of the traditional SPECTROX solution and supports the solution of more complex geometries with a more detailed spatial mesh and multiple resonance materials. The code generates both macroscopic and microscopic cross sections in the ISOTXS format with any selected number of energy groups. The user can specify which fission product isotopes are to be explicitly included in the microscopic burnup dependent ISOTXS library. Fission product library data can be generated for use with the MCNP code and burnup dependent applications. The cross section library data provided are based on ENDF/B version VI (69 group) and V (69 and 172 group) data. A revised 172 group library based on ENDF/B-VI is being generated with newer data and additional isotopes. This library will be made available at a later time. The code is variably dimensioned so that other group structures could be used. The source code and output format have been completely revised to reflect current coding practices and to permit display of the results on typical desk top monitors. The content of the output displayed is completely under the user's control.
 

5. METHOD OF SOLUTION

The methods of solution in WIMS-ANL remain unchanged from those used in the original WIMS-D4 code with the same resonance treatment and a choice of collision probability and DSN solutions for the simple lattice cell. The SUPERCELL option provides for the selection of supporting auxiliary cells that might represent the various different elements and varying spectra of the final SUPERCELL model. The resonance treatments where applicable are carried out in the auxiliary cells. These data are combined in the detailed SUPERCELL computation, and cross section data are generated for the selected edit regions and isotopes.
 

6. RESTRICTIONS OR LIMITATIONS

While the code is variably dimensioned, there are certain limits placed on some of the variables are the fixed container size. The maximum number of isotopes in the cross section library is set at 175, the maximum number of isotope entries on the ISOTXS file is set at 6000 (combined isotopes x burn steps), and the current container size is set at 6,000,000 words. These limits can be changed at compile time by modifying the Standard.inc and Iq.inc include files.
 

7. TYPICAL RUNNING TIME

Run times vary with the size and complexity of the problem.
 
 
 

8. COMPUTER HARDWARE REQUIREMENTS

WIMS-ANL runs on Unix under Sun Solaris and on PC under either Windows 95, 98, NT or Linux. The code, with only minor changes for the system calls for time/date information, would be expected to run under any of the flavors of Unix.
 

9. COMPUTER SOFTWARE REQUIREMENTS

The code has compiled successfully n Sun Solaris and on PC with the Lahey compilers F77L, LF90 and LF95 for PC and the g77 and GNU compilers under Reed Hat Linux 6.1.
 

10. REFERENCES

Documentation in pdf format on CD:

J. R. Deen, W. F. Woodruff, C. I. Costescu, and L. S. Leopando, "WIMS-ANL User Manual, Rev. 4," ANL/RERTR/TM-23 (December 2000).

"WIMS-D4 Winfrith Improved Multigroup Scheme Code System," Radiation Safety Information Computational Center Code Package CCC-576/WIMS-D4, Oak Ridge National Laboratory (October 1991).
 

11. CONTENTS OF CODE PACKAGE

Included in the package are the referenced documents in pdf format, source files, electronic information files, examples, and output files for PC and Unix/Linux versions of the code.
 

12. DATE OF ABSTRACT

April 2001.
 

KEYWORDS: CELL CALCULATION; CROSS SECTION PROCESSING; CROSS SECTIONS; REACTOR PHYSICS; BURNUP; FISSION PRODUCTS