1. NAME AND TITLE OF DATA LIBRARY
SENPRO: Compilation of Multigroup Sensitivity Profiles in SENPRO Format for Fast Reactor Core and Shield Benchmarks and Thermal Reactor Benchmarks.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
SENDIN
3. CONTRIBUTOR
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
The ORNL sensitivity analysis code system (FORSS) is a tool for studying relationships between cross sections, integral experiments, performance parameter predictions, and associated uncertainties. Fundamental to all studies involving sensitivity analysis are the relative sensitivities or sensitivity coefficients which are the derivatives of the logarithms of the performance parameters with respect to the logarithms of the nuclear data parameters. Especially important are the sensitivity profiles, which are the energy-dependent sensitivities. Therefore, a substantial part of the FORSS system is devoted to the calculation of the sensitivity coefficients and profiles; the remainder of the system is devoted to various applications which use these quantities.
5. APPLICATION OF THE DATA
Three types of response were considered: 1) the multiplication factor k, 2) a central capture-to-fission ratio, or 3) a central fission-to-fission ratio. (A central ratio is one for which the reactions considered are at the central point of the core.) The nuclear data included fission neutron yields and neutron reaction cross sections for fission, capture, elastic scattering, total inelastic scattering, and inelastic scattering from individual levels as well as from the continuum.
6. SOURCE AND SCOPE OF DATA
The sensitivities presented represent what are presently available at ORNL and are in no sense complete. There are omissions in assemblies, performance parameters, reaction types, and nuclides. However, it is believed that many of the most important coefficients are represented. These sensitivity coefficients have been compiled into a library for distribution in a computer-readable format.
A multigroup cross-section library was formed based on ORNL's 126/36 pseudo-composition independent fine-group LMFBR neutron-gamma coupled library which was, in turn, based on ENDF/B-IV data.
The sensitivities included the following nuclides:
O, Na, Fe, 235U, 238U, 239Pu, 240Pu, 241Pu, Cr, Ni.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
Not applicable.
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 360/91.
9. TYPICAL RUNNING TIME
Not applicable.
10. 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 Sentinal: Two Computer Codes to Assess the Effects of Nuclear Data Changes," ORNL/TM-5946 (ENDF-250) (July 1977).
11. CONTENTS OF LIBRARY
Included are the referenced documents and 1 tape cartridge in tar format which contains a number of neutron group profiles, the SENDIN retrieval code, input and output for the SENDIN sample problem, and the Fast Integral Benchmark Sensitivity Library.
12. DATE OF ABSTRACT
May 1985, updated February 1992.
KEYWORDS: CCCC INTERFACE FORMAT; SENSITIVITY PROFILES