This integral assessment quantifies the predictive capabilities of Fuel Analysis under Steady-state and Transients (FAST), a thermal-mechanical nuclear fuel performance code designed to analyze fuel behavior from beginning of life to burnup levels allowed by the U.S. Nuclear Regulatory Commission. FAST code calculations are shown to compare satisfactorily to a pre-selected set of experimental data with both steady-state and anticipated operating occurrence conditions and design basis accident transient operating conditions.
This document describes the assessment of FAST-1.2.2, the latest version of FAST, released April 2026.
Published: September 22, 2026
Citation
Geelhood K.J., C.E. Goodson, D.V. Colameco, D.F. Wray, W.G. Luscher, J. Corson, and J.J. Whitman. 2026.FAST-1.2.2: Integral Assessment. Richland, WA: Pacific Northwest National Laboratory. PNNL-39257.