Simplified Model of a High Burnup Spent Nuclear Fuel Rod under Lateral Impact Considering a Stress-Based Failure Criterion
Open Access
- 14 October 2021
- Vol. 11 (10), 1631
- https://doi.org/10.3390/met11101631
Abstract
The inventory of spent nuclear fuel (SNF) generated in nuclear power plants is continuously increasing, and it is very important to maintain the structural integrity of SNF for economical and efficient management. The cladding surrounding nuclear fuel must be protected from physical and mechanical deterioration, which causes fuel rod breakage. In this study, the material properties of the simplified beam model of a SNF rod were calibrated for a drop accident evaluation by considering the pellet–clad interaction (PCI) of the high burnup fuel rod. In a horizontal drop, which is the most damaging during a drop accident of SNF, the stress in the cladding caused by the inertia action of the pellets has a great effect on the integrity of the fuel rod. The failure criterion for SNF was selected as the membrane plus bending stress through stress linearization in the cross-sections through the thickness of the cladding. Because the stress concentration in the cladding around the vicinity of the pellet–pellet interface cannot be simulated in a simplified beam model, a stress correction factor is derived through a comparison of the simplified model and detailed model. The applicability of the developed simplified model is checked through dynamic impact simulations. The developed model can be used in cask level analyses and is expected to be usefully utilized to evaluate the structural integrity of SNF under transport and in storage conditions.Keywords
Funding Information
- Nuclear Safety and Security Commission (2106042)
This publication has 10 references indexed in Scilit:
- Development of Equivalent Beam Model of High Burnup Spent Nuclear Fuel Rods under Lateral Impact LoadingMetals, 2020
- Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditionsNuclear Engineering and Technology, 2019
- Simplified beam model of high burnup spent fuel rod under lateral load considering pellet-clad interfacial bonding influenceNuclear Engineering and Technology, 2019
- Structural integrity of a high-burnup spent fuel rod under drop impact considering pellet-clad interfacial bonding influenceNuclear Engineering and Design, 2018
- High burn-up spent nuclear fuel transport reliability investigationNuclear Engineering and Design, 2018
- Review of Spent Nuclear Fuel Dry Storage Demonstration Programs in USJournal of Nuclear Fuel Cycle and Waste Technology, 2017
- The impact of interface bonding efficiency on high-burnup spent nuclear fuel dynamic performanceNuclear Engineering and Design, 2016
- A New Method of Stress Linearization for Design by Analysis in Pressure Vessel DesignApplied Mechanics and Materials, 2014
- Shape optimization of a torus seal under multiple loading conditions based on the stress categories in the ASME code section IIINuclear Engineering and Design, 2011
- In-Reactor Performance of an Advanced PWR Fuel, PLUS7, for OPR1000s in KoreaJournal of Nuclear Science and Technology, 2008