Computer Programs
DLC-0045 ZZ-SENPRO/45C.
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DLC-0045 ZZ-SENPRO/45C.

ZZ SENPRO/45C, Multigroup Sensitivity Library for Fast Reactors, Thermal Reactors

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1. NAME

ZZ-SENPRO.

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-SENPRO/45C DLC-0045/03 Arrived 16-APR-2002

Machines used:

Package ID Orig. computer Test computer
DLC-0045/03 IBM 360 series
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3. DESCRIPTION

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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: RSICC, ENDF/B-IV

WEIGHTING SPECTRUM: Maxwellian and 1/E

 

U-L212

FORMAT: SENPRO format

NUMBER OF GROUPS: 57

NUCLIDES:

ORIGIN:

WEIGHTING SPECTRUM:

 

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

 

SENPRO is a package of data libraries containing multigroup sensitivity profiles for several fast reactor, thermal reactor and shielding benchmarks. Table 1 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 type

Assemblies

Nb of groups

Nb of profiles

Lab

References

Fast reactor

ZPR6-7,ZPR6-6A

ZPR3-56B,ZPR3-11

Godiva, Jezebel

126

650

ORNL

2

Fast reactor

ZPR3-48,ZPR6-7 ZPR6-6A,ZPR9-31

12

262

ANL

3,4

Fast reactor

LCCEWG

32

54

ORNL

5

Fast reactor

ZPR6-7

4

10

ORNL

5

Fast reactor

Combination of all the above

26

1263

ANL, ORNL

6

Shielding

CRBR Upper

Axial Shield

171

126

ORNL

7

Thermal Reactor

TRX-2

131

234

ORNL

8

Thermal Reactor

U-L212

57

94

ORNL

9

 

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4. METHODS

For descriptions of the procedures used in the generation of the data, see the references given in Table 1.

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9. STATUS
Package ID Status date Status
DLC-0045/03 16-APR-2002 Masterfiled Arrived
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10. REFERENCES
  • "Cross Section Evaluation Working Group Benchmark Specifications," 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.

DLC-0045/03, included references:
- 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).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0045/03 FORTRAN-IV
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Oak Ridge National Laboratory

                Oak Ridge, Tennessee, USA

And

                Argonne National Laboratory

                Argonne, Illinois, USA

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16. MATERIAL AVAILABLE
DLC-0045/03
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
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17. CATEGORIES
  • Z. Data

Keywords: data, fast reactors, sensitivity, shielding, thermal reactors.