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The Effect of Hydrogen in the Nuclear Fuel Cladding on the Oxidation under High Temperature and High Pressure Steam

고압 수증기하 산화에서 핵연료 피복관내 수소효과 연구

  • Jung, Yunmock (Department of Nuclear Engineering, Kyunghee University) ;
  • Jeong, Seonggi (KEPCO E&C, Nuclear System Department) ;
  • Park, Kwangheon (Department of Nuclear Engineering, Kyunghee University) ;
  • Noh, Seonho (Department of Nuclear Engineering, Kyunghee University)
  • 정윤목 (경희대학교 원자력공학과) ;
  • 정성기 (한국전력기술 원자로계통설계그룹) ;
  • 박광헌 (경희대학교 원자력공학과) ;
  • 노선호 (경희대학교 원자력공학과)
  • Received : 2014.01.15
  • Accepted : 2014.02.20
  • Published : 2014.02.28

Abstract

The characteristics of oxidation for the Zry-4 was measured in the $800^{\circ}C$ and high steam pressure (50 bar, 75 bar, 100 bar) conditions, using an apparatus for high pressure steam oxidation. The effect of accelerated oxidation by high-pressure steam was increased more than 60% in hydrogen-charged cladding than normal cladding. This difference between hydrogen charged claddings and normal claddings tends to be larger as the higher pressure. The accelerated oxidation effect of hydrogen charging cladding is regarded as the hydrogen on the metal layer affects the formation of the protective oxide layer. The creation of the sound monoclinic phase in Zry-4 oxidation influences reinforcement of corrosion-resistance of the oxide layer. The oxidation is estimated to be accelerated due to the creation of equiaxial type oxide film with lower corrosion resistance than that of columnar type oxide film. When tetragonal oxide film transformed into the monoclinic oxide film, surface energy of the new monoclinic phase reduced by hydrogen in the metal layer.

Keywords

References

  1. F. J. Erbacher, S. Leistikow, "Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review", ASTM STP939 (1987) 451.
  2. B. Cox, "Accelerated Oxidation of Zircaloy-2 in Supercritical Steam", AECL-4448 (1973) 7.
  3. I. L. Bramwell, T. J. Haste, D. Worswick, P. D. Parsons, "An Experimental Investigation into the Oxidation of Zircaloy-4 at Elevated Pressure in the 750 to $1000^{\circ}C$ Temperature Range", ASTM STP1245 (1994) 459.
  4. R. E. Pawel, J. V. Cathcart, J. J. Campbell, J. Nucl. Mater., 82 (1979) 136.
  5. K. Park, K. Kim, T. Yoo, K. Kim, Metal Mater. Int., 7(4) (2001) 368.
  6. ASTM, "Standard Test Method for Corrosion Testing of Prosucts of Zirconium, Hafnium, and Their Alloys in 633K or in Steam at 673K[Metric]", Annual Books of ASTM Standard section, 3 (1991) 49.
  7. H.-G. Kim, I.-H. Kim, S.-Y. Park, J.-Y. Park, Y.-H. Jeong, Kor. J. Met. Mater., 48(8) (2010) 717.
  8. J. Godlewski, J. P. Gros, M. Lambertin, J. F. Wadier J. Weidinger, "Raman Spectroscopy Study of the Tetragonal to Monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O18", ASTM STP, 1132 (1991) 395.
  9. J. B. Lightstone, J. P. Pemsler, Mater. Sci. Res., 4 (1969) 560.
  10. P. Kofstad, High Temperature Corrosion, Chap. 9, Elsevier, New York (1988).
  11. J. Godlewsk, J. P. Gros, M. Lambertin, J. F. Wadier H. Weidinger, ASTM STP 1132 (1991) 416.
  12. T. B. Massalski, Binary Alloy Phase Diagrams, American Society for Metals (1986).
  13. A. E. Hughes, H. st John, P. Kountouros, H. Schubert, J. Eur. Ceram. Soc., 15 (1995) 1125. https://doi.org/10.1016/0955-2219(95)00083-7