A Methodology for Developing a Probability Distribution for the Failure Enthalpy of High-Burnup Fuels via Simulation

References

• C. L. SMITH, V. N. SHAH, T.-M. KAO, and G. E. APOSTOLAKIS, “Incorporating Aging Effects into Probabilistic Risk Assessment—A Feasibility Study Utilizing Reliability Physics Models,” NUREG/CR-5632, U.S. Nuclear Regulatory Commission (2001).
   Google Scholar
• G. E. 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., August 22–26, 1999, p. 135, American Nuclear Society (1999).
   Google Scholar
• B. R. ELLINGWOOD and Y. MORI, “Probabilistic Methods for Condition Assessment and Life Prediction of Concrete Structures in Nuclear Power Plants,” Nucl. Eng. Des., 142, 155 (1993).
   Web of Science ®Google Scholar
• L. P. PAGANI, G. E. APOSTOLAKIS, and P. HEJZLAR, “The Impact of Uncertainties on the Performance of Passive Systems,” Nucl. Technol., 149, 129 (2005).
   Web of Science ®Google Scholar
• F. SCHMITZ and J. PAPIN, “High Burnup Effects on Fuel Behavior Under Accident Conditions: The Tests CABRI REP-Na,” J. Nucl. Mater., 270, 55 (1998).
   Google Scholar
• F. SCHMITZ, J. PAPIN, M. HAESSLER, J. NERVI, and P. PERMEZEL, “Investigation of the Behavior of High-Burnup PWR Fuel Under RIA Conditions in the CABRI Test Reactor,” Proc. 22nd Water Reactor Safety Information Mtg., NUREG/CP-0140, Vol. 2, p. 329, U.S. Nuclear Regulatory Commission (1995).
   Google Scholar
• T. FUKETA, Y. MORI, H. SASAJIMA, K. ISHIJIMA, and T. FUJISHIRO, “Behavior of High Burnup PWR Fuel Under a Simulated RIA Condition in the NSRR,” Proc. Specialist Mtg. Transient Behavior of High Burnup Fuel, Cadarache, France, September 12–14, 1995; see also NEA/CSNI/R(95)22, p. 59 (1996).
   Google Scholar
• T. FUKETA, H. SASAJIMA, Y. MORI, and K. ISHIJIMA, “Fuel Failure and Fission Gas Release in High Burnup PWR Fuels Under RIA Conditions,” J. Nucl. Mater., 248, 249 (1997).
   Web of Science ®Google Scholar
• L. YEGOROVA, “Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and UO2 Fuel (VVER Type) Under Reactivity Initiated Accident Conditions: Review of Research Program and Analysis of Results,” NUREG/IA-0156, Vol. 1, IPSN 99/08-1, NSIRRC 2179, U.S. Nuclear Regulatory Commission (1999).
   Google Scholar
• F. LEMOINE, “High Burnup Fuel Behavior Related to Fission Gas Effects Under Reactivity Initiated Accidents (RIA) Conditions,” J. Nucl. Mater., 248, 238 (1997).
   Web of Science ®Google Scholar
• H. M. CHUNG and T. F. KASSNER, “Cladding Metallurgy and Fracture Behavior During Reactivity-Initiated Accidents at High Burnup,” Nucl. Eng. Des., 186, 411 (1998).
   Web of Science ®Google Scholar
• D. J. DIAMOND, B. P. BROMLEY, and A. L. ARONSON. “Studies of the Rod Ejection Accident in a PWR,” Technical Report W-6382, Brookhaven National Laboratory (2002).
   Google Scholar
• “An Assessment of Postulated Reactivity-Initiated Accidents (RIAs) for Operating Reactors in the U.S.,” ML040920189, U.S. Nuclear Regulatory Commission (2004).
   Google Scholar
• M. E. CUNNINGHAM, C. E. BEYER, P. G. MEDVEDEV, and G. A. BERNA, “FRAPTRAN: A Computer Code for Transient Analysis of Oxide Fuel Rods,” NUREG/CR-6739, U.S. Nuclear Regulatory Commission (2001).
   Google Scholar
• D. D. LANNING, C. E. BEYER, and C. L. PAINTER, “FRAPCON-3: Modifications to Fuel Rod Material Properties and Performance Models for High-Burnup Application,” NUREG/CR-6534, U.S. Nuclear Regulatory Commission (1997).
   Google Scholar
• R. O. MONTGOMERY, N. WAECKEL, and R. YANG, “Topical Report on Reactivity Initiated Accidents: Bases for RIA Fuel Failures and Core Coolability Criteria,” Report 1002865, Electric Power Research Institute (2002).
   Google Scholar
• M. LIMBACK, “Corrosion and Hydriding Performance of Zircaloy-2 and Zircaloy-4 Cladding Materials in PWRs,” Proc. Int. Topl. Mtg. Light Water Reactor Fuel Performance, West Palm Beach, Florida, April 17–21, 1994, p. 286, American Nuclear Society (1994).
   Google Scholar
• G. E. APOSTOLAKIS, “A Commentary on Model Uncertainty,” Proc. Workshop Model Uncertainty: Its Characterization and Quantification, College Park, Maryland, October 20–22, 1993, p. 13, University of Maryland Printing Services (1995); see also NUREG/CP-0138, U.S. Nuclear Regulatory Commission (1994).
   Google Scholar
• J. LEWINS, “The Adiabatic Fuchs-Nordheim Model and Non-Dimensional Solutions,” Ann. Nucl. Energy, 22, 681 (1995).
   Google Scholar
• B. E. BOYACK, A. T. MOTTA, K. L. PEDDICORD, C. A. ALEXANDER, R. C. DEVENEY, B. M. DUNN, T. FUKETA, K. E. HIGAR, L. E. HOCHREITER, S. LANGENBUCH, F. J. MOODY, M. E. NISSLEY, J. PAPIN, G. POTTS, D. W. PRUITT, J. RASHID, D. H. RISHER, R. J. ROHRER, J. S. TULENKO, K. VALTONEN, N. WAECKEL, and W. WIESENACK, “Phenomenon Identification and Ranking Tables (PIRTs) for Rod Ejection Accidents in Pressurized Water Reactors Containing High Burnup Fuel,” NUREG/CR-6742, U.S. Nuclear Regulatory Commission (2001).
   Google Scholar