REFERENCES
- M. D. CARELLI, “IRIS: Final Technical Progress Report,” STD-ES-03-40, Westinghouse Electric Company (Nov. 3, 2003).
- H. SHEN, “Advanced Feedwater Control for Next Generation Nuclear Power Systems,” PhD Dissertation, North Carolina State University (2006).
- J. M. DOSTER and P. J. TURINSKY, “Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration—Final Report Volume 2: IRIS Simulator Development and Measurement Sensitivity Analysis,” DE-FG07-07ID14895/UTNE/2011-4, University of Tennessee (May 2011).
- B. E. BOYACK et al., “Quantifying Reactor Safety Margins, Parts 1-6,” Nucl. Eng. Des., 119, 1 (1990).
- F. D’AURIA, N. DEBRECIN, and G. M. GALASSI, “Outline of the Uncertainty Methodology Based on Accuracy Extrapolation,” J. Nucl. Technol., 109, 1, 21 (1995).
- C. FREPOLI, K. OHKAWA, and R. M. KEMPER, “Realistic Large Break LOCA Analysis of AP1000 with ASTRUM,” Proc. 6th Int. Conf. Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4–8, 2004, Atomic Energy Society of Japan (2004).
- D. G. CACUCI, Sensitivity and Uncertainty Analysis, Vol. 1, CRC Press (2000).
- H. S. ABDEL-KHALIK, “Adaptive Core Simulation,” PhD Dissertation, North Carolina State University (2004).
- M. A. JESSEE, “Cross-Section Adjustment Techniques for BWR Adaptive Simulation,” PhD Dissertation, North Carolina State University (2008).
- T. E. STOVER and P. J. TURINSKY, “Experiment Optimization to Reduce Nuclear Data Uncertainties in Support of ReactorDesign,” Nucl. Technol., 180, 216 (2012).
- A. TARANTOLA, Inverse Problem Theory and Methods for Model Parameter Estimation, Society for Industrial and Applied Mathematics, Philadelphia, Pennsylvania (2005).
- D. G. CACUCI and M. IONESCU-BUJOR, “Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation—I: Mathematical Framework,” Nucl. Sci.Eng., 165, 18 (2010).
- J. W. HINES et al., “Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration,” DE-FG07-07ID14895/UTNE/2010-1, University of Tennessee (Jan. 2010).
- A. N. TIKHONOV, Numerical Methods for the Solution of Ill-Posed Problems, Kluwer Academic Publishers (1995).
- H. W. ENGL and W. GREVER, “Using the L-Curve for Determining Optimal Regularization Parameters,” Numerische Mathematik, 69, 25 (1994).
- J. W. HINES et al., “Advanced Instrumentation and Con-trol Methods for Small and Medium Reactors with IRIS Demonstration,” DE-FG07-07ID14895/UTNE/2009-4, University of Tennessee (Oct. 2009).
- D. HIGDON et al., “Combining Field Data and Computer Simulation for Calibration and Prediction,” SIAM J. Sci. Comput., 26, 2, 448 (2004).
- A. GELMAN, G. O. ROBERTS, and W. R. GILKS, “Ef-ficient Metropolis Jumping Rules,” Bayesian Statistics 5, pp. 599–607, J. M. BERNARDO et al., Eds., Oxford Univer-sity Press (1996).
- P. MULLER, “A Generic Approach to Posterior Integration and Gibbs Sampling,” Tech. Rep., ISDS, Duke University (1993).
- K. M. HANSON and G. S. CUNNINGHAM, “Posterior Sampling with Improved Efficiency,” Proc. SPIE, 3338, 371 (1998).
- N. E. TODREAS and M. S. KAZIMI, Nuclear Systems, Hemisphere Publishing Corporation, New York (1990).
- RELAP5/MOD3 Code Manual Volume IV: Models and Correlations (Draft), EG&G Idaho, Inc., Idaho Falls, Idaho (June 1990).
- D. L. HAGRMAN, “MATPRO—Version 11, A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior,” NUREG/CR-0497, Idaho National Engineering Laboratory (Feb. 1979).
- “Kewaunee Nuclear Power Plant Safety Evaluation for Amendment 168—Measurement Uncertainty Recapture Power Uprate,” U.S. Nuclear Regulatory Commission (2003).
- S. KIRKPATRICK, C. D. GELATT, and M. P. VECCHI, “Optimization by Simulated Annealing,” Science, 220, 671 (1983).
- “FORMOSA-B Code Methodology and Usage Manual, Version 3.2,” North Carolina State University (2004).