Description: Full-length nuclear fuel rods were tested in a furnace to simulate the slow heating rates postulated for commercial pressurized water reactor fuel rods exposed to an overheating event in a storage cask. Fuel rod temperatures and internal gas pressures were monitored during the test and are presented along with mensural data for cladding. Metallography of the cladding provided data on grain growth, hydriding, oxidation, cladding stresses, and the general nature of the failures.
Date: January 1, 1983
Creator: Guenther, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department