FRAPTRAN 1.4: Integral Assessment (NUREG/CR-7023, Volume 2, PNNL-19400, Volume 2)
On this page:
Download complete document
This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.
Manuscript Completed: August 2010
Date Published: March 2011
K.J. Geelhood, W.G. Luscher, C.E. Beyer
Pacific Northwest National Laboratory
P.O. Box 999
Richland, WA 99352
M.E. Flanagan, NRC Project Manager
NRC Job Code N6609
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 1.4, which is the latest version of FRAPTRAN, released May 4, 2009.