Sensitivity and Uncertainty of OECD Benchmark Ringhals-1 TRACE/PARCS Stability Prediction

References

• “Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation,” IAEA Safety Reports Series No. 52, International Atomic Energy Agency (2008).
   Google Scholar
• Y. Xu, T. Downar, K. Ivanov, J. Veldovi, A. Petruzzi, and J. Staudenmeier, “Analysis of the OECD/NEA Ringhals Instability Benchmark with TRACE/PARCS,” Proc. Topl. Mtg. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Palais des Papes, Avignon, France, September 12–15, 2005, French Section of American Nuclear Society/Société Française d’Energie Nucléaire (2005).
   Google Scholar
• Y. Xu, T. Downar, K. Ivanov, A. Petruzzi, F. Mag-Gini, R. MirÓ, and J. Staudenmeier, “Methodologies for BWR Stability Analysis with TRACE/PARCS,” Proc. Topl. Mtg. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Palais des Papes, Avignon, France, September 12–15, 2005, French Section of American Nuclear Society/Société Française d’Energie Nucléaire (2005).
   Google Scholar
• C. Aguirreet al., “Benchmarking of Transient Codes Against Cycle 19 Stability Measurements at Leibstadt Nuclear Power Plant (KKL),” Proc. Int. Conf. Physics of Reactors (PHYSOR 2010), Pittsburgh, Pennsylvania, May 9–14, 2010, American Nuclear Society (2010) (CD-ROM).
   Google Scholar
• L. Belblidia, G. Grandi, and C. Aguirre, “SIMULATE-3K Stability Benchmarking and Predictive Calculations of Leibstadt,” Proc. Int. Conf. Physics of Reactors (PHYSOR 2008), Interlaken, Switzerland, September 14–19, 2008.
   Google Scholar
• G. Grandiet al., “BWR Stability Analyses with SIMULATE-3K Benchmark Against Measured Plant Data,” Prog. Nucl. Energy, 53, 6, 583 (Aug. 2011); http://www.sciencedirect.com/science/journal/01491970/53/6.
   Google Scholar
• D. Panayotov and M. Thunman, “POLCA-T Code Validation Against Peach Bottom 2 End of Cycle 2 Low-Flow Stability Tests,” Proc. M&C 2003, Gatlinburg, Tennessee, April 6–10, 2003, American Nuclear Society (2003) (CD-ROM).
   Google Scholar
• Y. Xu, T. Downar, R. Walls, K. Ivanov, J. Staudenmeier, and J. March-Lueba, “Application of TRACE/PARCS to BWR Stability Analysis,” Ann. Nucl. Energy, 36, 3 (Apr. 2009).
   Google Scholar
• D. G. Cacuci, Sensitivity and Uncertainty Analysis. Volume 1 Theory, Chapman & Hall/CRC (2003).
   Google Scholar
• H. Glaeser, “GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications,” Sci. Technol. Nucl. Installations, 2008 (2008).
   Google Scholar
• A. Petruzzi and F. D’Auria, “Approaches, Relevant Topics, and Internal Method for Uncertainty Evaluation in Predictions of Neutronie System Codes,” Sci. Technol. Nucl. Installations, 2008 (2008).
   Google Scholar
• M. F. Triola, Elementary Statistics Using Excel, 3rd ed., pp. 748–755 and p. 825, Pearson Education, Boston, Massachusetts (2007).
   Google Scholar
• T. Lefvert, “Ringhals 1 Stability Benchmark,” NEA/NSC/DOC (96)22, Nuclear Energy Agency/Nuclear Science Committee (1996).
   Google Scholar
• Y. Xu, “DRARMAX User’s Manual,” Purdue University.
   Google Scholar
• G. Alibertiet al., “Nuclear Data Sensitivity, Uncertainty and Target Accuracy Assessment for Future Nuclear Systems,” Ann. Nucl. Energy, 33, 700 (2006).
   Web of Science ®Google Scholar
• I. Nemes, “Refueling Design Safety Limits of PAKS NPP,” in “Safety Margins of Operating Reactors Analysis of Uncertainties and Implications for Decision Making,” IAEA TEC-DOC Series No. 1332, International Atomic Energy Agency (Jan. 22, 2003).
   Google Scholar
• R. Kuramotoet al., “Absolute Measurement of bef Based on Rossi-a Experiments and the Two-Region Model in the IPEN/MB-01 Research Reactor,” Nucl. Sci. Eng, 158, 272 (2008).
   Web of Science ®Google Scholar
• I. Matssonet al., “On-Site g-Ray Spectroscopic Measurements of Fission Gas Release in Irradiated Nuclear Fuel,” Appl. Radiat. Isot., 65, 36 (2007).
   Web of Science ®Google Scholar
• B. Neykovet al., “NUPEC BWR Full-Size Fine-Mesh Bundle Test (BFBT) Benchmark, Volume I: Specifications,” NEA/NSC/DOC(2005)5, Organisation for Economic Cooperation and Development/Nuclear Energy Agency Nuclear Science Committee/Nuclear Energy Agency Committee on Safety of Nuclear Installations/U.S. Nuclear Regulatory Commission (2006).
   Google Scholar
• T. Wickettet al., “Report of the Uncertainty Method Study for Advanced Best Estimate Thermal Hydraulic Code Applications,” NEA/CSNI R (97)35, Vol. 1, p. 14, Organisation for Economic Co-operation and Development/Committee on Safety of Nuclear Installations (1998).
   Google Scholar
• A. Petruzzi and F. D’auria, “Thermal-Hydraulic System Codes in Nuclear Reactor Safety and Qualification Procedures,” Sci. Technol. Nucl. Installations, 2008 (2008).
   Google Scholar
• D. Panayotov and M. Thunman, “POLCA-T Code Validation Against Peach Bottom 2 End of Cycle 2 Low-Flow Stability Tests,” Proc. M&C2003, Gatlinburg, Tennessee, April 6–10, 2003, American Nuclear Society (2003) (CD-ROM).
   Google Scholar
• A. Prosek and B. Mavko, “Practical Use of Uncertainty Evaluation Methods in Slovenia,” in “Safety Margins of Operating Reactors Analysis of Uncertainties and Implications for Decision Making,” IAEA TECDOC Series No. 1332, International Atomic Energy Agency (Jan. 22, 2003).
   Google Scholar
• W. Wulffet al., “Quantifying Reactor Safety Margins: Application of CSAU to a LBLOC; Part 3: Assessment and Ranging Parameters,” Nucl. Eng. Des., 119, 1, 1 (May 1990).
   Google Scholar