Thermal Analysis of AFIP-2 Experiment in the Advanced Test Reactor

摘要

A thermal analysis was performed at the Idaho National Laboratory on the ATR Full-Size Plates in Center Flux Trap Position (AFIP) experiment. The AFIP fuels consist of monolithic and dispersion fuels fabricated using high-density uranium metallic fuel alloys clad in aluminum. The thermal analysis was performed to determine fuel temperatures and safety margins of the test while being irradiated in the Advanced Test Reactor (ATR). The overall experiment description and various types of fuel proposed for this experiment is presented in Reference [1]. The purpose of this experiment is to provide the necessary data to support the conversion of civilian facilities using high enriched uranium (HEU) to low enriched uranium (LEU) fuels and targets. The purpose of this paper is to present the thermal analysis performed on the AFIP irradiation experiment in the ATR in support of the U.S. Department of Energy (DOE) Reduced Enrichment for Research and Test Reactor (RERTR) program.