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 and anticipated operating occurrence (AOO) conditions and design basis accident (DBA) transient operating conditions.
This document describes the assessment of FAST-1.1, the latest version of FAST, released April 2022.
Abstract
Published: October 21, 2025
Citation
Geelhood K.J., D.J. Richmond, D.V. Colameco, T.J. Zipperer, W.G. Luscher, L. Kyriazidis, and C.E. Goodson, et al. 2022.FAST-1.1: Integral Assessment - Developed under NQA-1-2017. Richland, WA: Pacific Northwest National Laboratory. PNNL-32771.