Use of sensitivity and uncertainty analysis to select benchmark experiments for the validation of computer codes and data

Nuclear Science and Engineering

Volumn 145, Issue 2, 2003, Pages 196-212

  Elam, K R ^a   Rearden, B T ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BENCHMARKING; COMPUTER AIDED ENGINEERING; SENSITIVITY ANALYSIS; UNCERTAIN SYSTEMS;

CRITICALITY ANALYSIS VALIDATION; CRITICALITY CODE;

NUCLEAR ENGINEERING;

EID: 0142149070     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE03-A2376     Document Type: Article

References (28)

1. B. L. Broadhead and B. T. Rearden, "Foundations for Sensitivity-Based Criticality Validation Techniques," Trans. Am. Nucl. Soc., 83, 93 (2000).
2. B. L. Broadhead, "Uncertainty Analysis Methods for S/U Criticality Validation Techniques," Trans. Am. Nucl. Soc., 83, 95 (2000).
3. B. B. Broadhead, R. L. Childs, and C. M. Hopper, "Illustrative Examples of Least Squares Methods for Criticality Safety," Trans. Am. Nucl. Soc., 83, 100 (2000).
4. B. T. Rearden, C. M. Hopper, K. R. Elam, B. L. Broadhead, and P. B. Fox, "Prototypic Applications of Sensitivity and Uncertainty Analysis for Experiment Needs," Trans. Am. Nucl. Soc., 83, 103 (2000).
5. M. E. Dunn and B. T. Rearden, "Application of Sensitivity and Uncertainty Analysis Methods to a Validation Study for Weapons-Grade Mixed-Oxide Fuel," Proc. Embedded Topl. Mtg. Practical Implementation of Nuclear Criticality Safety, Reno, Nevada, November 11-15, 2001, American Nuclear Society (2001) (CD-ROM).
6. "American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors," ANSI/ANS-8.1, American Nuclear Society (1983).
7. B. T. Rearden and K. R. Elam, "Investigations and Recommendations on the Use of Existing Experiments in Criticality Safety Analysis of Nuclear Fuel Cycle Facilities for Weapons-Grade Plutonium," ORNL/TM-2001-262, Oak Ridge National Laboratory (June 2002).
8. S. O. Bader et al., "MOX Fuel Fabrication Facility Nuclear Criticality Validation Approach," Proc. Embedded Topl. Mtg. Practical Implementation of Nuclear Criticality Safety, Reno, Nevada, November 11-15, 2001, American Nuclear Society (2001) (CD-ROM).
9. "International Handbook of Evaluated Criticality Safety Benchmark Experiments," NEA/NSC/DOC(95)03, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (1999).
10. B. L. Broadhead, B. T. Rearden, C.M. Hopper, J. J. Wagschal, and C. V. Parks, "Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques," Nucl. Sci. Eng. (to be published).
11. E. M. Oblow, "Sensitivity Theory from a Differential Viewpoint," Nucl. Sci. Eng., 59, 187 (1976).
12. W. M. Stacey, Jr., "Variational Estimates and Generalized Perturbation Theory for the Ratios of Linear and Bilinear Functionals," J. Math. Phys., 13, 1119 (1972)
13. W. M. Stacey, Jr., "Variational Estimates of Reactivity Worths and Reaction Rate Ratios in Critical Nuclear Reactors," Nucl. Sci. Eng., 48, 444 (1972).
14. L. N. Usachev, "Perturbation Theory for the Breeding Ratio and for Other Number Ratios Pertaining to Various Reactor Processes," J. Nucl. Energy A/B, 18, 571 (1964).
15. A. Gandini, "A Generalized Perturbation Method for Bilinear Functionals of the Real and Adjoint Neutron Fluxes," J. Nucl. Energy, 21, 755 (1967).
16. C. R. Weisbin et al., "Application of FORSS Sensitivity and Uncertainty Methodology to Fast Reactor Benchmark Analysis," ORNL/TM-5563, Oak Ridge National Laboratory (1976).
17. M. L. Williams, B. L. Broadhead, and C. V. Parks, "Eigenvalue Sensitivity Theory for Resonance-Shielded Cross Sections," Nucl. Sci. Eng., 138, 177 (2001).
18. B. L. Broadhead, C. M. Hopper, R. L. Childs, and C. V. Parks, "Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation," NUREG/CR-6655, Vols. 1 and 2 (ORNL/TM-13692/V1 and V2), Oak Ridge National Laboratory (Nov. 1999).
19. B. L. Broadhead, C.M. Hopper, K. R. Elam, B. T. Rearden, and R. L. Childs, "Criticality Safety Applications of S/U Validation Methods," Trans. Am. Nucl. Soc., 83, 107 (2000).
20. M. E. Dunn, "PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices," ORNL/TM-1999/235 (NUREG/CR-6650), Oak Ridge National Laboratory (June 2000).
21. "SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing and Evaluations," NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2R6), Vols. I, II, and III, Oak Ridge National Laboratory (May 2000); see also CCC-545, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
22. B. T. Rearden, "Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques," Nucl. Sci. Eng. (to be published).
23. J.D. Smith III, "Processing ENDF/B-V Uncertainty into Multigroup Covariance Matrices," ORNL/TM-7221, Oak Ridge National Laboratory (1980).
24. B. T. Rearden and R. L. Childs, "Prototypical Sensitivity and Uncertainty Analysis Codes for Criticality Safety with the SCALE Code System," Trans. Am. Nucl. Soc., 83, 98 (2000).
25. J. J. Lichtenwalter, S. M. Bowman, M. D. Dehart, and C. M. Hopper, "Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages," NUREG/CR-6361 (ORNL/TM-13211), Oak Ridge National Laboratory (Mar. 1997).
26. S. R. Bierman and E. D. Clayton, "Critical Experiments with Low-Moderated Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium," Nucl. Sci. Eng., 61, 370 (1976).
27. S. R. Bierman, and E. D. Clayton, "Critical Experiments to Measure the Neutron Poisoning Effects of Copper and Copper-Cadmium Plates," Nucl. Sci. Eng., 55, 58 (1974).
28. S. R. Bierman, B. M. Durst, and E. D. Clayton, "Critical Experiments Measuring the Reactivity Worths of Materials Commonly Encountered as Fixed Neutron Poisons," BNWL-2129, Battelle Pacific Northwest Laboratories (Oct. 1976).