Open AccessPNNL Stress/Strain Correlation for Zircaloy
Author(s) -
Kenneth J. Geelhood,
C.E. Beyer,
Walter G. Luscher
Publication year - 2008
Language(s) - English
Resource type - Reports
DOI - 10.2172/969740
Subject(s) - cladding (metalworking) , national laboratory , nuclear engineering , nuclear fuel , zirconium alloy , forensic engineering , strain (injury) , materials science , environmental science , engineering , composite material , medicine , engineering physics , alloy
Pacific Northwest National Laboratory (PNNL) was tasked with incorporating cladding mechanical property data into the Nuclear Regulatory Commission (NRC) fuel codes, FRAPCON-31 and FRAPTRAN2, by the NRC Office of Nuclear Reactor Research. The objective of that task was to create a mechanical model that can calculate true stress, true strain, and the possible failure of the fuel rod cladding based on uniaxial test data