Modeling and analysis framework for steam explosion energetics evaluations in uranium-aluminum fueled reactors

摘要

FCIMOD code is a computer code used to predict Fuel Coolant Interaction (FCI) energetics. This paper presents modeling changes implemented into the FCIMOD code. The modified code renamed ''FCIMOD(center dot)ORNL,'' is being used to perform safety analysis calculations for the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory. In addition to the modeling changes, this paper also compares computational predictions to experimental results and discusses the overall applicability of the modeling method to nuclear reactor safety studies.