FRAPCON-3 Updates, Including Mixed-Oxide Fuel Properties (NUREG/CR-6534, Volume 4)
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Manuscript Completed: May 2005
Date Published: May 2005
D. D. Lanning, C. E. Beyer, K.J.Geelhood
Pacific Northwest National Laboratory
Richland, WA 99352
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code Y6586
The FRAPCON-3 code has been altered by a number of additions to form version FRAPCON-3.3. The major changes include an improved model for the urania fuel pellet thermal conductivity; the addition of mixed plutonia-urania oxide (MOX) fuel pellet thermal properties and other parameters to facilitate analysis of MOX fuel rod performance; and the addition of corrosion and hydrogen pickup parameters appropriate to advanced cladding types. This volume contains descriptions and discussions of these and other revisions.
The document also contains code-data comparisons of MOX fuel temperatures used to verify the MOX fuel pellet thermal conductivity model, and similar comparisons for urania fuel rods. The total sequence of code revisions that have led from the last-published version of FRAPCON-3 (NUREG/ CR-6534, Volume 2, 1997) to the latest issued version, FRAPCON-3.3, is also given.