Journal of the Korean institute of surface engineering (한국표면공학회지)

The Korean Institute of Surface Engineering (한국표면공학회)
권호 표지

Zricaloy-4 Oxidation Kinetics in High-Pressure High-Temperature Steam and Application to Accident Analysis

고압 고온 수증기에서 지르칼로이-4 산화반응 정량화 및 사고해석에의 응용

  • Published : 2002.12.01
Download PDF
⟨ Previous Next ⟩

Abstract

Empirical equations for the oxide thickness and the weight gain of Zircaloy-4 cladding during the oxidation in high temperature, high pressure steam have been developed. Firstly, the empirical equations for oxide thickness in 1 atm steam in 700~100$0^{\circ}C$ were made, then, the enhancement factor for the steam pressure effects on Zircaloy-4 cladding oxidation in high temperature steam was added. Based on the analysis of the weight fraction of dissolved oxygen in metal layer, empirical equations for the weight gain of Zircaloy-4 in high pressure, high temperature steam were developed. We compare the developed empirical equations with the Baker-Just correlation. The Baker-Just correlation can give a non-conservative estimation of oxidation of Zircaloy-4, depending on the steam pressure. These developed empirical equations can be used for the correct estimation of oxidation of Zircaloy-4 during accident analysis.

Keywords

References

  1. L. Baker and L. C. Just : 'Study of Metal Water Reactions at High Temperature III, Ex-perimental and Theohcal Studies of Zirconium-Water Reaction', ANL-6548 (1962)
  2. J.P. Pemsler : Electrochem. Technol. 4 (1966) 128
  3. R.G. Ballinger : J. Nucl. Mater., 62 (1976) 213 https://doi.org/10.1016/0022-3115(76)90017-9
  4. S. Leistikow and G. Schanz : Nuclear Eng. and Design, 103 (1987) 65 https://doi.org/10.1016/0029-5493(87)90286-X
  5. S. Leistikow and G. Schanz : Werkstoffe und Korrosion, 36 (1985) 105 https://doi.org/10.1002/maco.19850360302
  6. R.E. Pawel : J. Electrochem. Soc., 126 (1979) 1111 https://doi.org/10.1149/1.2129228
  7. R.E. Pawel, J.V. Cathcart, and R.A.McKee : J Electochem. Soc 126 (1979) 1105 https://doi.org/10.1149/1.2129227
  8. A.F. Brown, M.O. Tucker, and T. Healey : J Nucl. Mater., 105 (1982) 93 https://doi.org/10.1016/0022-3115(82)90455-X
  9. R.R. Biederman, H. Ocken, and R.D. Sisson : Jr, J. Nucl. Mater., 97 (1981) 265 https://doi.org/10.1016/0022-3115(81)90474-8
  10. J.T. Prater and E.L. Courtright 'High Tempe rature Oxidation of Zircaloy-4 in Steam and Steam-Hydrogne Environments', NUREG/CR 4476 (1986)
  11. J.P. Pemsler : J. Electrochem. Soc., 113 (1966) 1241 https://doi.org/10.1149/1.2423796
  12. J. Godlewski, J.P. Gros, M. Lambertin, J.F. Wadier, and H. Weidmger : 'Raman Spectroscopy Study of the Tetragonal-to-Monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of 0-18' ASTM STP 1132 (1991) 416
  13. F. Gazarolli, H. Seidal, R. Tricont and G.P. Gros : 'Oxide Growth Mechanism in Zriconiu malloys', ASTMSTP1132 (1991) 395
  14. P. Barbehs : J. Nucl. Mater., 226 (1995) 34 https://doi.org/10.1016/0022-3115(95)00108-5
  15. B. Cox : 'Accelerated Oxidation of Zircaloy-2 in Superchtical Steam,' AECL-4448 (1973)
  16. Y.S.Kim, D.Min, S.Kim, S.Ro, Y.Ok, and M. Park : 'High Pressure Steam Corrosion and Hydridmg of Zircaloy-4', International Topical Meeting on LWR Fuel Performance, Port land, U.S.A. (1997)
  17. R. E. Pawal, J. V. Cathcart and J. J. Camp-bell : J. Nucl. Mat., 82 (1979) 129 https://doi.org/10.1016/0022-3115(79)90045-X
  18. I.L.Bramwell, T.J.Haste, D.Worswick : and P. D.Parsons : "An Expehmental Investigation into the Oxidation of Zirca1oy-4 at Elevated Pressures in the 750 to $1000^{\circ}C$ Temperature Range', ASTM STP 1245 (1994) 450
  19. K. Park, K. Kim, and J. Whang : 'Pressure Effects on High Temperature Zircaloy-4 Oxidation tn Steam', International Topical Meeting on LWR Fuel Performance, Park City, Utah, U. S.A. (2000)
  20. S. Kass : J. Nucl. Mater., 28 (1969) 315
  21. I.K. Dawson, G. Long, W.E. Seddon, and J.F. White : J. Nucl. Mater., 25 (1968) 179 https://doi.org/10.1016/0022-3115(68)90044-5
  22. F. Garzarolli : 'Waterside Corrosion of Zirca-loy-Clad Fuel Rods in a PWR Environment' ASTM STP 754 (1982) 430
  23. E. Hillner : 'Corrosion of Zirconium-Base Alloys - An Overview', ASTM STP 633 (1977) 211
  24. B. Cox : AECL-6784 (1980)
  25. K. Park, T. Yoo, and K. Kim : to be published
  26. A. Denis, E. Moyano, and E.A. Garcia : J Nucl. Mater. 110 (1982) 11 https://doi.org/10.1016/0022-3115(82)90402-0
  27. K. Park, K. Kim, and T. Yoo : 'Pressure Effe-cts on High Temperature Steam Oxidation of Zirca1oy-4', Proceedings of the Symposium on Nuclear Materials and Fuel 2000, Taejon, Korea, August (2000)
  28. B. Cox : J. Nucl. Mater., 29 (1969) 50 https://doi.org/10.1016/0022-3115(69)90126-3
  29. D.H. Bradhurst and P.M. Heuer : J. NuclMater., 37 (1970) 35 https://doi.org/10.1016/0022-3115(70)90180-7
  30. J. Roy and G. David : J. Nucl. Mater., 37 (1970) 71 https://doi.org/10.1016/0022-3115(70)90183-2
  31. P. Barberis : J. Nucl. Mater., 226 (1995) 34 https://doi.org/10.1016/0022-3115(95)00108-5
  32. J. Nakamura, M. Hashimoto and S. Kawasa ki : J. Nucl. Mater., 200 (1993) 256 https://doi.org/10.1016/0022-3115(93)90336-W