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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 175 - 181 (7page)
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초록· 키워드
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A failed spent fuel rod with 53,000 MWd/tU from a nuclear power plant was characterized, and the fissionproducts 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 compareand analyze, the results of the failed fuel rod. In the failed fuel rod, the oxide layer represented 10 μmof the boundary of the cladding, and 35 μm of the region outside the cladding. By comparison, in thesound fuel rod, the oxide layer was 8 μm, observed in the cladding boundary region. The cladding innersurface corrosion and the resulting fuel-cladding bonding were investigated using an EPMA. Zirconiumexisted in the bonding layer of the (U, Zr)O compound beyond the pellet cladding interaction gap of 20μm, and composition of UZr2O3 was observed in the failed fuel rod. This paper presents the results ofthe EPMA examination of a spent fuel specimen, and a technique to analyze fission products in the pellet-cladmechanical interaction region.
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