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Technical Paper

A BEPU Analysis Separating Epistemic and Aleatory Errors to Compute Accurate Dryout Power Uncertainties

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Pages 170-183 | Published online: 10 Aug 2017

References

  • A. Petruzzi and F. D’auria, “Thermal-Hydraulic System Codes in Nuclear Reactor Safety and Qualification Procedures,” Sci. Technol. Nucl. Installations, 2008, doi:10.1155/2008/460795 (2008).
  • A. Petruzzi, N. Muellner, F. S. D’auria, and O. Mazzantini, “The BEPU (Best-Estimate Plus Uncertainty) Challenge in Current Licensing of Nuclear Reactors,” Proc. 14th Int. Topl. Mtg. Nuclear Reactor Thermalhydraulics (NURETH-14), Toronto, Ontario, Canada, September 25–30, 2011.
  • A. Prosek and B. Mavko, “The State-of-the-Art Theory and Applications of Best-Estimate Plus Uncertainty Methods,” Nucl. Technol., 158, 69 (2007).
  • C. Frepoli, “An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model,” Sci. Technol. Nucl. Installations, 2008, doi:10.1155/2008/498737 (2008).
  • A. Bucalossi, A. Petruzzi, M. Kristof, and F. D’auria, “Comparison Between Best-Estimate-Plus-Uncertainty Methods and Conservative Tools For Nuclear Power Plant Licensing,” Nucl. Technol., 172, 29 (2010).
  • N. Popov, “Best Estimate and Uncertainty Analysis for CANDU Reactors,” presented at 8th Seminar on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology (3D S.UN.COP), Hamilton, Ontario, Canada, October 8–26, 2007.
  • P. Sermer and F. Hoppe, “Statistical Foundation for a BEPU-Like Methodology in Nuclear Safety Analyses: An Overview,” presented at 11th Seminar on Scaling, Uncertainty and 3D Coupled Calculations in Nuclear Technology (3D S.UN-.COP), Institute for Energy, Joint Research Center, Petten, The Netherlands, Oct. 18–Nov. 5, 2010.
  • D. R. Novog and P. Sermer, “A Statistical Methodology for Determination of Safety Systems Actuation Setpoints Based on Extreme Value Statistics,” Sci. Technol. Nucl. Installations, 2008, doi:10.1155/2008/290373 (2008).
  • P. Sermer and C. Olive, “Probabilistic Approach to Compliance with Fuel Channel Power License Limits,” Trans. Am. Nucl. Soc., 72, 332 (1995).
  • P. Sermer et al., “Monte-Carlo Computation of Neutron Over-Power Protection Trip Setpoints Using Extreme Value Statistics,” Proc. 24th Annual Conf. Canadian Nuclear Society, Toronto, Canada, June 8–11, 2003, Canadian Nuclear Society (2003).
  • A. C. Cullen and H. C. Frey, Probabilistic Techniques in Exposure Assessment, Plenum Press, New York (1999).
  • G. Apostolakis, “The Distinction Between Aleatory and Epistemic Uncertainties Is Important: An Example from the Inclusion of Aging Effects into PSA,” Proc. Int. Topl. Mtg. Probabilistic Safety Assessment (PSA ’99), Washington, D.C., Aug. 22–25, 1999, American Nuclear Society.
  • Y. Orechwa, “Best-Estimate Analysis and Decision Making Under Uncertainty,” Proc. BE 2004: Int. Mtg. Updates in Best Estimate Methods in Nuclear Installations Safety Analysis, Washington, D.C., November 14–18, 2004, American Nuclear Society (2004) (CD-ROM).
  • G. Hahn, “Understanding Statistical Intervals,” Ind. Eng., 45 (Dec. 1970).
  • P. Sermer et al., “Using Statistical Inference for Decision Making in Best Estimate Analysis,” Proc. 29th Annual Conf. Canadian Nuclear Society, Toronto, Canada, June 2008.
  • “Heat Transport System,” in “CANTEACH”; http://canteach.candu.org (Jan. 1996).
  • W. S. Liu, R. K. Leung, and J. C. Luxat, “Overview of TUF Code for CANDU Reactors,” Proc. 5th Int. Conf. Simulation Methods in Nuclear Engineering, Montréal, Quebec, September 1996, Canadian Nuclear Society (1996).
  • “BEMUSE Phase III Report, Uncertainty and Sensitivity Analysis of the LOFT L2-5 Test,” OECD/NEA/CSNI/R (2007)4, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (Oct. 2007).
  • C. Chauliac, “A EU Simulation Platform for Nuclear Reactor Safety: Multi-Scale and Multi-Physics Calculations, Sensitivity and Uncertainty Analysis,” presented at 7th European Commission Conf. Euroatom Research and Training in Reactor Systems (FISA 2009), Prague, Czech Republic, June 22–24, 2009.
  • A. Petruzzi and F. D’auria, “Approaches, Relevant Topics, and Internal Method for Uncertainty Evaluation in Predictions of Thermal-Hydraulic System Codes,” Sci. Technol. Nucl. Installations, 2008, doi:10.1155/2008/325071 (2008).
  • Uncertainty Analysis, Y. Ronen, Ed., CRC Press, Boca Raton, Florida (1988).
  • 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).
  • A. Petruzzi, D. G. Cacuci, and F. D’auria, “Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation—II: Application to a Blowdown Benchmark Experiment,” Nucl. Sci. Eng., 165, 45 (2010).
  • J. H. Wilkinson, The Algebraic Eigenvalue Problem, Oxford University Press (1965).
  • W. H. Press, B. P. Flanner, S. A. Teukolsky, and W. T. Vetterling, Numerical Recipes, p. 529, Cambridge University Press, Cambridge (1986).

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