Abstract
This article presents the development of a grid-to-rod fretting (GTRF) modeling methodology that utilizes dynamic mortar contact. We leverage a recently developed computational framework for modeling thermomechanical contact in dynamic simulations from the nuclear fuel performance code Bison. Usage of mortar contact ensures a smooth distribution of normal and frictional contact forces, displacements, and velocities on the contact interface, thus facilitating an accurate computation of wear. The integration within an advanced nuclear fuel performance code enables analysis of complex interactions between the fuel, cladding, and spacer grid. Such interactions include swelling, creep, fuel fragmentation, burnup, plenum pressure, and fission gas release. Our methodology is demonstrated via the modeling of two spacer grid geometries and the influence of fuel-cladding mechanical contact on the generation of fretting wear.
| Original language | English |
|---|---|
| Article number | 104793 |
| Journal | Progress in Nuclear Energy |
| Volume | 163 |
| Early online date | Jul 1 2023 |
| DOIs | |
| State | Published - Sep 2023 |
Keywords
- Bison
- Grid-to-rod fretting wear
- Mortar finite element method
- Nuclear fuel performance
- Simulation
INL Publication Number
- INL/JOU-22-69798
- 141949
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