Detailed Fission Power 2D-Mapping of AFIP-2 Experiment in ATR CFT Position. 13th International Symposium on Reactor Dosimetry (Preprint)

摘要

The NNSA (National Nuclear Security Administration) RERTR (Reduced Enrichment for Research and Test Reactors) program assigned INL (Idaho National Laboratory) the responsibility of developing and demonstrating high uranium density research reactor fuel forms to enable the use of low enriched uranium (LEU) in the research reactors around the world. A series of full-size fuel plate irradiation tests are proposed for the ATR (Advanced Test Reactor). Labeled the AFIP (ATR Full-size-plates In center flux trap Position) experiments, these tests will be conducted in the ATR center flux trap. The AFIP-2 experiment will contain two full size fuel plates fabricated at the Oak Ridge National Laboratory-Y-12 (ORNL). The nominal fuel zone is rectangular in shape having a designed length of 21.5-inches (54.6l-cm), width of 1.6-inches (4.064-cm), and uniform thickness of 0.014-inches (0.03556-cm).