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http://dx.doi.org/10.14773/cst.2019.18.5.175

Investigation of Pellet-Clad Mechanical Interaction in Failed Spent PWR Fuel  

Jung, Yang Hong (Korea Atomic Energy Research Institute)
Baik, Seung Je (Korea Atomic Energy Research Institute)
Publication Information
Corrosion Science and Technology / v.18, no.5, 2019 , pp. 175-181 More about this Journal
Abstract
A failed spent fuel rod with 53,000 MWd/tU from a nuclear power plant was characterized, and the fission products and oxygen layer in the pellet-clad mechanical interaction region were observed using an EPMA (Electron Probe Micro-Analyzer). A sound fuel rod burned under similar conditions was used to compare and analyze, the results of the failed fuel rod. In the failed fuel rod, the oxide layer represented $10{\mu}m$ of the boundary of the cladding, and $35{\mu}m$ of the region outside the cladding. By comparison, in the sound fuel rod, the oxide layer was $8{\mu}m$, observed in the cladding boundary region. The cladding inner surface corrosion and the resulting fuel-cladding bonding were investigated using an EPMA. Zirconium existed in the bonding layer of the (U, Zr)O compound beyond the pellet cladding interaction gap of $20{\mu}m$, and composition of UZr2O3 was observed in the failed fuel rod. This paper presents the results of the EPMA examination of a spent fuel specimen, and a technique to analyze fission products in the pellet-clad mechanical interaction region.
Keywords
Pellet-clad mechanical interaction; A fission product; Hot-cell; Bonding layer;
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