Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques

Nuclear Science and Engineering

Volumn 146, Issue 3, 2004, Pages 340-366

  Broadhead, B L ^a   Rearden, B T ^a   Hopper, C M ^a   Wagschal, J J ^b   Parks, C V ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b HEBREW UNIVERSITY OF JERUSALEM   (Israel)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; BENCHMARKING; COMPUTATIONAL METHODS; CONVERGENCE OF NUMERICAL METHODS; DATA REDUCTION; DATABASE SYSTEMS; ESTIMATION; LEAST SQUARES APPROXIMATIONS; RADIOISOTOPES; URANIUM;

ENERGY-DEPENDENT SENSITIVITY COEFFICIENTS; GENERALIZED LINEAR-LEAST-SQUARES METHODOLOGY (GLLSM);

NUCLEAR ENERGY;

EID: 1842588313     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE03-2     Document Type: Article

References (27)

1. "Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors," ANSI/ANS-8.1-1998, American Nuclear Society (1998).
2. 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), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (1997).
3. R. K. DISNEY, "A Review of the Current State-of-the-Art Methodology for Handling Bias and Uncertainty in Performing Criticality Safety Evaluations," INEL-94/0251, UC-501, Idaho National Engineering Laboratory (1994).
4. "SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing and Evaluations," NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III, CCC-545, Radiation Safety Information Computational Center (May 2000).
5. R. L. CHILDS, "SEN1: A One-Dimensional Cross-Section Sensitivity and Uncertainty Module for Criticality Safety Analysis," NUREG/CR-5719 (ORNL/TM-13738), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (1999).
6. B. T. REARDEN, "Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques," Nucl. Sci. Eng., 145, XXX (2004).
7. American National Standard for Criticality Safety Criteria for the Handling, Storage, and Transportation of LWR Fuel Outside Reactors, ANSI/ANS-8.17-1984 (R 1997), American Nuclear Society (1997).
8. H. R. DYER and C. V. PARKS, "Recommendations for Preparing the Criticality Safety Evaluation of Transport Packages," NUREG/CR-5661 (ORNL/TM-11936), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (1997).
9. E. M. OBLOW, "Sensitivity Theory from a Differential Viewpoint," Nucl. Sci. Eng., 59, 187 (1976).
10. W. M. STACEY, Jr., "Variational Estimates and Generalized Perturbation Theory for the Ratios of Linear and Bilinear Functionals," J. Math. Phys., 13, 1119 (1972); see also W. M. STACEY, Jr., "Variational Estimates of Reactivity Worths and Reaction Rate Ratios in Critical Nuclear Reactors," Nucl. Sci. Eng., 48, 444 (1972).
11. W. M. STACEY, Jr., "Variational Estimates and Generalized Perturbation Theory for the Ratios of Linear and Bilinear Functionals," J. Math. Phys., 13, 1119 (1972); see also W. M. STACEY, Jr., "Variational Estimates of Reactivity Worths and Reaction Rate Ratios in Critical Nuclear Reactors," Nucl. Sci. Eng., 48, 444 (1972).
12. L. N. USACHEV, "Perturbation Theory for the Breeding Ratio and for Other Number Ratios Pertaining to Various Reactor Processes," J. Nucl. Energy 18, parts A/B, 571 (1964).
13. A. GANDINI, "A Generalized Perturbation Method for Bilinear Functionals of the Real and Adjoint Neutron Fluxes," J. Nucl. Energy, 21, 755 (1967).
14. C. R. WEISBIN, J. H. MARABLE, J. L. LUCIUS, E. M. OBLOW, F. R. MYNATT, R. W. PEELLE, and F. G. PEREY, "Application of FORSS Sensitivity and Uncertainty Methodology to Fast Reactor Benchmark Analysis," ORNL/TM-5563, Oak Ridge National Laboratory (Dec. 1976); see also "Application of Sensitivity and Uncertainty Methodology to Fast Reactor Integral Experiment Analysis," Nucl. Sci. Eng., 66, 307 (1978).
15. C. R. WEISBIN, J. H. MARABLE, J. L. LUCIUS, E. M. OBLOW, F. R. MYNATT, R. W. PEELLE, and F. G. PEREY, "Application of FORSS Sensitivity and Uncertainty Methodology to Fast Reactor Benchmark Analysis," ORNL/TM-5563, Oak Ridge National Laboratory (Dec. 1976); see also "Application of Sensitivity and Uncertainty Methodology to Fast Reactor Integral Experiment Analysis," Nucl. Sci. Eng., 66, 307 (1978).
16. M. L. WILLIAMS, B. L. BROADHEAD, and C. V. PARKS, "Eigenvalue Sensitivity Theory for Resonance-Shielded Cross Sections," Nucl. Sci. Eng., 138, 177 (2001).
17. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03, Nuclear Energy Agency Nuclear Science Committee of the Organization for Economic Cooperation and Development (1999).
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 andV2), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (1999).
19. S. GOLOUGLU, C. M. HOPPER, and B. T. REARDEN, "Extended Interpretation of Sensitivity Data for Benchmark Areas of Applicability," Trans. Am. Nuc. Soc., 88, 77 (2003).
20. G. PALMIOTTI and M. SALVATORES, "Use of Integral Experiments in the Assessment of Large Liquid-Metal Fast Breeder Reactor Basic Design Parameters," Nucl. Sci. Eng., 87, 333 (1984).
21. J. D. SMITH III and B. L. BROADHEAD, "Multigroup Covariance Matrices for Fast Reactor Studies," ORNL/TM-7389, Oak Ridge National Laboratory (1981).
22. R. E. McFARLANE, R. J. BARRETT, D. W. MUIR, and R. M. BOICOURT, "The NJOY Nuclear Data Processing System: User's Manual," LA-7584-M, Los Alamos National Laboratory (1978).
23. M. E. DUNN, "PUFF-III: A Code for Processing ENDF Uncertainty Data into Multigroup Covariance Matrices," ORNL/TM-1999/235 (NUREG/CR-6650), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (2000).
24. A. PAZY, G. RAKAVY, I. REISS, J. J. WAGSCHAL, A. YA'ARI, and Y. YEIVIN, "The Role of Integral Data in Neutron Cross-Section Evaluation," Nucl. Sci. Eng., 55, 280 (1974).
25. R. L. PEREL, J. J. WAGSCHAL, and Y. YEIVIN, "PV-Surveillance Dosimetry and Adjustment: Review of Several Significant Oral Laws," in "Reactor Dosimetry: Radiation Metrology and Assessment," J. G. WILLIAMS, D. W. VAHAR, F. H. RUDDY, and D. M. GILLIAM, Eds., ASTM STP 1398, p. 486, American Society for Testing and Materials (2001).
26. J. D. SMITH III, "Processing ENDF/B-V Uncertainty into Multigroup Covariance Matrices," ORNL/TM-7221, Oak Ridge National Laboratory (1980).
27. B. L. BROADHEAD, C. M. HOPPER, S. C. FRANKLE, J. F. BRIESMEISTER, R. C. LITTLE, and J. J. WAGSCHAL, "Further Investigations of NIST Water Sphere Discrepancies," ORNL/TM-2000/173, Oak Ridge National Laboratory (2000).