DLC-0045 ZZ-SENPRO.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-SENPRO.

3. DESCRIPTION OF PROBLEM OR FUNCTION



%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%


  ZPR6-7, ZPR6-6A, ZPR3-56B, ZPR3-11, Godiva, Jezebel

  ===================================================



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 126



  NUCLIDES:



  ORIGIN:



  WEIGHTING SPECTRUM:





  ZPR3-48, ZPR6-7, ZPR6-6A, ZPR9-31

  =================================



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 12



  NUCLIDES: Pu, U, Na, Fe, Ni, Cr, C, B



  ORIGIN: ENDF/B-IV



  WEIGHTING SPECTRUM:





  LCCEWG

  ======



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 32



  NUCLIDES: U, Pu



  ORIGIN: ENDF/B-IV, ENDF/B-V



  WEIGHTING SPECTRUM:





  ZPR6-7

  ======



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 4



  NUCLIDES: Pu, U



  ORIGIN: ENDF/B-IV



  WEIGHTING SPECTRUM:





  COMBINATION OF ALL THE ABOVE

  ============================



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 26



  NUCLIDES:



  ORIGIN: ENDF/B-IV



  WEIGHTING SPECTRUM:





  CRBR

  ====



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 171



  NUCLIDES: iron, steel and sodium



  ORIGIN: ENDF/B-IV + TSF experimental results



  WEIGHTING SPECTRUM:





  TRX-2

  =====



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 131



  NUCLIDES: Fuel (U-235, U-238), Void, Clad (Al), Moderator (H, O)



  ORIGIN: RSIC, ENDF/B-IV



  WEIGHTING SPECTRUM: Maxwellian and 1/E





  U-L212

  ======



  FORMAT: SENPRO format



  NUMBER OF GROUPS: 57



  NUCLIDES:



  ORIGIN:



  WEIGHTING SPECTRUM:



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SENPRO is a package of data libraries containing multigroup sensitivity profiles for several fast reactor, thermal reactor and shielding benchmarks. Table I lists the various sensitivity profiles along with references describing the procedures used in their creation. Some of the references listed are included as part of the  documentation  distributed with the data:



         Table 1. Sensitivity Profile Libraries Included

                  In DLC-45C/SENPRO



Benchmark                    Number   Number of

Type Assemblies of Groups Profiles Lab References

Fast      ZPR6-7,ZPR6-6A,

Reactor   ZPR3-56B,ZPR3-11,   126        650       ORNL      2

          Godiva, Jezebel



Fast      ZPR3-48,ZPR6-7,

Reactor   ZPR6-6A,ZPR9-31      12        262       ANL      11,12



Fast

Reactor   LCCEWG               32         54       ORNL      3



Fast

Reactor   ZPR6-7                4         10       ORNL      3



Fast      Combination of                           ANL,

Reactor   All the Above        26       1263       ORNL      4



Shielding CRBR Upper

          Axial Shield        171        126       ORNL     10



Thermal

Reactor   TRX-2               131        234       ORNL      5



Thermal

Reactor   U-L212               57         94       ORNL      6

4. METHOD OF SOLUTION

For descriptions of the procedures used in the  generation of the data, see the references given in Table I.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

6. TYPICAL RUNNING TIME:

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:

10. REFERENCES

-   "Cross Section Evaluation Working Group Benchmark Specifica-
    tions,"
    BNL 19302 (ENDF-202), November 1974.

-   C.R. Weisbin (ORNL), J.H. Marable (ORNL), J. Hardy, Jr. (BAPL),
    and R.D. McKnight (ANL),
    "Sensitivity Coefficient Compilation for CSEWG Data Testing
    Benchmarks",
    ENDF-265, to be published.

- Informal Notes (September 1978).
- J. H. Marable, J. L. Lucius, and C. R. Weisbin,
"Compilation of Sensitivity Profiles for Several CSEWG Fast Reactor Benchmarks,"
ORNL-5262 (March 1977).
- E. M. Bohn, I. K. Olson, and K. E. Freese,
"A Compilation of Cross-Section Sensitivity Coefficients for ZPR6-6A,
ZPR6-7, and ZPR3-48,"  ZPR-TM-240 (May 1976).
- R. D. McKnight and I. K. Olson,
"Nuclear Data Sensitivity Coefficients for the Advanced Fuels
Program Carbide Benchmark Critical Assembly," ZPR-TM-280, (June 1977).
- J. H. Marable and C. R. Weisbin,
"Uncertainties in the Breeding Ratio of a Large LMFBR,"
Advances in Reactor Physics, CONF-780401, Proceedings of an ANS Topical Meeting,
April 10-13, 1978.
- E. M. Oblow and C. R. Weisbin,
"Fast Reactor Shield Sensitivity Studies for Steel-Sodium-Iron Systems,"
Proceedings of the Fifth International Conference on Reactor Shielding, Science
Press, April 1977.
- E. T. Tomlinson, J. L. Lucius, and J. D. Drischler,
"A Compendium of Energy-Dependent Sensitivity Profiles for the TRX-2 Thermal
Lattice", ORNL-5336 (ENDF-253), (July 1977).
- R. L. Childs, G. de Saussure, J. L. Lucius, J. D. Drischler, V. C. Baker, and
J. A. Marable, "Sensitivity and Uncertainty Analysis for Mixed-Oxide Thermal
Reactor Parameters," to be published
J. H. Marable, J. D. Drischler, and C. R. Weisbin,
"Sendin and Sentinel: Two Computer Codes to Assess the Effects of Nuclear Data
Changes", ORNL/TM-5946 (ENDF-250) (July 1977).

11. MACHINE REQUIREMENTS:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by:
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.
and
Argonne National Laboratory
Argonne, Illinois, U.S.A.

DLC045.F01 126 N grp sensitivity profiles(650) for CSEWG benchmark
DLC045.F02 12 N grp profiles (262) for CSEWG benchmarks (7/80)
DLC045.F03 32 N grp profiles (54) for 2D model of large LMFBR
DLC045.F04 4 N grp profiles (10) for ZPR-6/7 for LCCEWG
DLC045.F05 26 N grp profiles (1263) for CSEWG benchmarks (7/80)
DLC045.F06 171 N grp profiles (126) for Na, S.S. Fe shield (7/80)
DLC045.F07 131 grp profiles (94) for TRX-2 thermal lattice benchmark
DLC045.F08 57 N grp profiles (234) for U-L212 mixed oxide thermal bench.
DLC045.F09 SENDIN retrieval code
DLC045.F10 SENDIN JCL and input data for SENDIN sample problem
DLC045.F11 SENDIN sample problem output
D045.PDF Documentation in electronic format
045i3691.txt List of files