본문 바로가기
KERD
논문KCI 등재

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

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류금속공학

초록

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.

Abstract

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.

참고문헌 (13)

  1. J. Julien, , Proc. Top Fuel 2012, pp.96~ (2012), European Nuclear Society
  2. B. Cox, , J. Nucl. Mater, 172, pp.249~ (1990)
  3. A. Denis, , J. Nucl. Eng. Des, 223, pp.211~ (2003)
  4. N. Marchal, , Comput. Mater. Sci, 45, pp.821~ (2009)
  5. H. Kleykamp, , J. Nucl. Mater, 131, pp.230~ (1985)
  6. Characterisation of PWR Cladding Hulls from Commercial Reprocessing, "R. Restani", ~, pp.Technical Reprot NTB-92-13 (1992)
  7. Y. H. Jung, , J. Nucl. Mater, 377, pp.444~ (2008)
  8. Chemical interaction between UO2 fuel and Zircaloy clad, "Y.-k Ha", KAERI, ~, pp.KAERI (2004), AR-697
  9. K. Maeda, "The measurement and evaluation of fuel cladding chemical interaction between Fuels and cladding materials", KAERI-JAEA Experts Meeting (2010)
  10. Y. Nishino, , J. Nucl. Mater, 228, pp.346~ (1996)
  11. D. J. Park, , J. Nucl. Mater, 412, pp.233~ (2011)
  12. H. C. Suk, , J. Nucl. Eng. Des, 165, pp.81~ (1996)
  13. Y. H. Jung, , Proc. KNS Spring Meeting (2019)

관련 논문AI추천

이 간행물의 다른 논문 (7건)