Computer Programs

DLC-0045 ZZ-SENPRO/45C.

DLC-0045 ZZ-SENPRO/45C.

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

NAME, COMPUTER, PROBLEM, SOLUTION, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

[ top ]

1. NAME

ZZ-SENPRO.

[ top ]

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

[ top ]

3. DESCRIPTION

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

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

[ top ]

4. METHODS

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

[ top ]

9. STATUS

Package ID	Status date	Status
DLC-0045/03	16-APR-2002	Masterfiled Arrived

[ top ]

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).

[ top ]

12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
DLC-0045/03	FORTRAN-IV

[ top ]

15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Oak Ridge National Laboratory

Oak Ridge, Tennessee, USA

And

Argonne National Laboratory

Argonne, Illinois, USA

[ top ]

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

[ top ]

17. CATEGORIES

Z. Data

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