NESC0355 MC**2-2NESC.

1. NAME OR DESIGNATION OF PROGRAM:  MC**2-2.

3. DESCRIPTION OF PROBLEM OR FUNCTION

MC**2-2 solves the neutron slowing-down equations using basic neutron data derived from ENDF/B  data files to determine spectra for use in generating multigroup neutron cross sections. The current edition includes the ability to  treat all ENDF/B-V representations, high-order PL scattering representations, a free-format input processor, isotope mixing, delayed neutron processing, and flexibility in output data selection.

4. METHOD OF SOLUTION

The extended transport P1, B1, consistent P1, and consistent B1 fundamental mode ultra-fine-group equations are solved using continuous slowing-down theory and multigroup methods.  Fast and accurate resonance integral methods are used in the narrow  resonance resolved and unresolved resonance treatments. Multigroup neutron cross sections are generated for arbitrary group structures. A hyper-fine-group integral transport slowing-down calculation is available as an option.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The program uses variable dimensioning throughout so that computer storage requirements depend on a variety of problem parameters. Space requirements range from approximately 400K to 1000K bytes on IBM equipment depending on the complexity of the problem.

6. TYPICAL RUNNING TIME

A 1740-group consistent P1 homogeneous twelve-isotope problem with 27 broad groups requires about 6.5 minutes of CPU time on an IBM 370/195. The same problem requires approximately 30% less CP time on the CDC 7600.

7. UNUSUAL FEATURES OF THE PROGRAM

Extreme flexibility is provided in specifying the rigor of a calculation including a choice of four distinct slowing-down treatments: multigroup, improved and standard  Greuling-Goertzel continuous slowing-down, and integral transport theory. All binary data transfers are localized in CCCC standard soubroutines REED/RITE. Broad group cross section files may be generated in the ARC System XS.ISO (reference 2) and CCCC ISOTXS (reference 3) formats.

8. RELATED AND AUXILIARY PROGRAMS

This edition supercedes previous releases of the MC**2-2 program and the earlier MC**2 program. Improved physics algorithms and increased computational efficiency are incorporated. Input data files required by MC**2-2 may be generated from ENDF/B data by the code ETOE2. The hyper-fine-group integral transport theory module of MC**2-2, RABANL, is an improved  version of the RABBLE/RABID codes. Many of the MC**2-2 modules are used in the SDX code.

10. REFERENCES

- L.C. Just, H. Henryson, II, A.S. Kennedy, S.D. Sparck, B.J.
  Toppel, and P.M. Walker,
  The System Aspects and Interface Data Sets of the Argonne Reactor
  Computation (ARC) System,
  ANL-7711, April 1971.
- Standard Interface Files and procedures for Reactor Physics Codes,   Version III,
  LA-5486-MS, February 1974.

-  H. Henryson II, J. Toppel and C. G. Stenberg:
    MC**2-2: A Code Calculate Fast Neutron Spectra and
             Multigroup Cross Sections
    NESC Report, ANL-8144(ENDF 239) (June 1976)

11. MACHINE REQUIREMENTS

A large amount of fast peripheral storage is  required. Storage requirements depend on problem complexity but vitually any reasonable problem may be executed on IBM equipment with 800K bytes or CDC equipment with 50,000 words od SCM and 100,000 words of directly addressable LCM.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The IBM version of MC**2-2 may be executed under OS or VS operating systems and compiled using the FORTRAN H or program product compilers with the highest level of optimization. The CDC 7600 version of MC**2-2 has been implemented on both the Lawrence Berkeley Laboratory and Brookhaven Laboratory computers with their respective COKE/SCOPE operating systems. The SEGMENTATION LOADER is required and directly  addressable LCM is used. The code was compiled using the FORTRAN Extended compiler under OPT=2 optimization.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Subsequent CDC 7600 system changes at BNL reduced the size of the directory tables used, obsoleting the operating instructions given on pages 221-229 and Appendix F of ANL-8144.

15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by:
H. Henryson, II, B.J. Toppel, and C.G. Stenberg
Applied Physics Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439

File name	File description	Records
NESC0355_03.003	INFORMATION FILE	39
NESC0355_03.004	MC**2-2 SOURCE FILE	58800
NESC0355_03.005	SYSTEM FORTRAN + COMPASS ROUTINE	654
NESC0355_03.006	SEGMENTATION LOADER DIRECTIVES	48
NESC0355_03.007	ORIGINAL JCL AND SAMPLE PROBLEM INPUT	154
NESC0355_03.008	LIBGEN FORTRAN SOURCE	1527
NESC0355_03.009	1ST EBCDIC CHARACTER LIBRARY	133118
NESC0355_03.010	2ND EBCDIC CHARACTER LIBRARY	221037
NESC0355_03.011	3RD EBCDIC CHARACTER LIBRARY	178767