Irradiation Test of MOX Fuel Rods Fabricated by Attrition-Milling and Analysis of In-Pile Data with COSMOS Code

REFERENCES

• L. J. OTT and R. N. MORRIS, “Irradiation Tests of Mixed-Oxide Fuel Prepared with Weapons-Derived Plutonium,” J. Nucl. Mater., 371, 314 (2007).
   Web of Science ®Google Scholar
• Y. H. KOO, B. H. LEE, and D. S. SOHN, “COSMOS: A Computer Code to Analyze LWR UO2 and MOX Fuel up to High Burnup,” Ann. Nucl. Energy, 26, 47 (1999).
   Web of Science ®Google Scholar
• B. H. LEE, Y. H. KOO, J. Y. OH, J. S. CHEON, and D. S. SOHN, “Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2 Fuels,” Nucl. Technol., 157, 53 (2007).
   Web of Science ®Google Scholar
• L. J. OTT, T. TVERBERG, and E. SARTORI, “Mixed-Oxide (MOX) Fuel Performance Benchmarks,” Ann. Nucl. Energy, 36, 375 (2009).
   Web of Science ®Google Scholar
• Y. W. LEE, H. S. KIM, S. H. KIM, C. Y. JOUNG, S. H. NA, G. LEDERGERBER, P. HEIMGARTNER, M. POUCHON, and M. BURGHARTZ, “Preparation of Simulated Inert Matrix Fuel with Different Powders by Dry Milling Method,” J. Nucl. Mater., 274, 7 (1999).
   Web of Science ®Google Scholar
• M. BILLAUX and J. VLIET, “Impact of Fuel Heterogeneities on Fission Gas Release for LWR U-Pu Mixed Oxide Fuels,” presented at International Atomic Energy Agency Specialists’ Meeting Water Reactor Fuel Element Performance Computer Modelling, Windermere, United Kingdom, April 9–13, 1984.
   Google Scholar
• R. L. GIBBY, “The Effect of Plutonium Content on the Thermal Conductivity of (U,Pu)O2 Solid Solution,” J. Nucl. Mater., 38, 163 (1971).
   Web of Science ®Google Scholar
• Y. H. KOO, B. H. LEE, J. S. CHEON, and D. S. SOHN, “Modeling and Parametric Studies of the Effect of Inhomogeneity on Fission Gas Release in LWR MOX Fuel,” Ann. Nucl. Energy, 29, 271 (2002).
   Web of Science ®Google Scholar
• H. S. KIM, C. Y. JOUNG, B. H. LEE, J. Y. OH, Y. H. KOO, and P. HEIMGARTNER, “Applicability of CeO2 as a Surrogate for PuO2 in a MOX Fuel Development,” J. Nucl. Mater., 378, 98 (2008).
   Web of Science ®Google Scholar
• C. BAGGER, M. MOGENSEN, and C. T. WALKER, “Temperature Measurements in High Burnup UO, Nuclear Fuel: Implications for Thermal Conductivity, Grain Growth and Gas Release,” J. Nucl. Mater., 211, 11 (1994).
   Web of Science ®Google Scholar
• H. K. JOO, J. W. YOO, and J. M. NOH, “The Verification of HELIOS-1.6 for MOX Fuels,” KAERI/TR-1682/2000, Korea Atomic Energy Research Institute.
   Google Scholar
• W. WIESENACK, B. H. LEE, and D. S. SOHN, “Irradiation Test of MOX Fuel in the Halden Reactor and the Analysis of Measured Data with the Fuel Performance Code COSMOS,” Nucl. Eng. Technol., 37, 317 (2005).
   Google Scholar
• Ch. HELLWIG, P. HEIMGARTNER, H. S. KIM, and G. LEDERGERBER, TM-43-03-08, Paul Scherrer Institut (2003).
   Google Scholar
• B. H. LEE, Y. H. KOO, J. S. CHEON, J. Y. OH, and D. S. SOHN, “AUnified Thermal Conductivity Model for LWRMOX Fuel Considering Its Microstructural Characteristics,” J. Nucl. Sci. Technol., Suppl. 3, 705 (2002).
   Google Scholar
• B. H. LEE, Y. H. KOO, H. S. KIM, J. Y. OH, D. S. SOHN, and C. DEGUELDRE, “Comparison of a Measured and Calculated Thermal Conductivity for an Attrition-Milled MOX Fuel,” presented at Enlarged Halden Project Group Mtg., May 2008.
   Google Scholar
• B. H. LEE, Y. H. KOO, H. K. JOO, J. S. CHEON, J. Y. OH, and D. S. SOHN, “Radial Power Density Distribution of MOX Fuel Rods,” KAERI/TR-2155/2002, Korea Atomic Energy Research Institute (April 2002).
   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, Vol. 1, U.S. Nuclear Regulatory Commission (1997).
   Google Scholar
• C. VITANZA, E. KOLSTAD, and V. GRAZIANI, “Fission Gas Release from UO2 Pellet Fuel at High Burn-Up,” Proc. Topl. Mtg. Light Water Reactor Fuel Performance, Portland, Oregon, April 29–May 3, 1979, American Nuclear Society (1979).
   Google Scholar
• Y. H. KOO, B. H. LEE, and D. S. SOHN, “Analysis of Fission Gas Release and Gaseous Swelling in UO2 Fuel Under the Effect of External Restraint,” J. Nucl. Mater., 280, 86 (2000).
   Web of Science ®Google Scholar