FRAPTRAN 1.5: Integral Assessment (NUREG/CR-7023, Volume 2, Revision 1)
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Manuscript Completed: May 2014
Date Published: October 2014
K. J. Geelhood, W. G. Luscher, and J. M. Cuta
Pacific Northwest National Laboratory
Richland, WA 99352
P. Raynaud, NRC Project Manager
NRC Job Code V6197
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001
An integral assessment has been performed for the U.S. Nuclear Regulatory Commission by Pacific Northwest National Laboratory to quantify the predictive capabilities of FRAPTRAN, a transient fuel behavior code designed to analyze fuel behavior during a range of power and coolant transients with fuel burnup up to 62 gigawatt-days per metric ton of uranium. The FRAPTRAN code calculations are shown to compare satisfactorily to a set of experimental data from reactivity-initiated accident and loss-of-coolant-accident operating conditions.
This document describes the assessment of FRAPTRAN-1.5, which is the latest version of FRAPTRAN, released May, 2014.
Page Last Reviewed/Updated Friday, May 13, 2016