An integral assessment has been performed to quantify the predictive capabilities of 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 (NRC). FAST
code calculations are shown to compare satisfactorily to a preselected set of experimental data
with both steady-state, anticipated operating occurence (AOO) and design basis transient operating
conditions.
This document describes the assessment of FAST-1.0, which is the latest version of FAST, released
February 2020.