The US Nuclear Regulatory Commission (USNRC) is tasked with licensing of safe spent fuel storage and transportation systems. A subset of this responsibility is to investigate and understand the structural performance of these systems. In a joint effort between staff at the Pacific Northwest National Laboratory (PNNL) and the USNRC, computational studies were performed to predict the structural response of spent nuclear fuel when subject to an end impact accident. In this study, the structural performance of a typical Pressurized Water Reactor (PWR) fuel assembly is evaluated utilizing the ANSYS®/LS-DYNA® finite element analysis (FEA) code.
Revised: June 8, 2011 |
Published: November 19, 2004
Citation
Adkins H.E., B.J. Koeppel, and D.T. Tang. 2004.Spent Nuclear Fuel Structural Response when Subject to an End Impact Accident. In 2004 American Society of Mechanical Engineers, Pressure Vessels & Piping Division, 483, 207-214. New York, New York:American Society of Mechanical Engineers.PNNL-SA-41214.