Pressure Effects on Zircaloy-4 Steamside Corrosion and Hydrogen Pick-up

  • Published : 1998.10.01

Abstract

Experiments on the steamside corrosion and hydrogen pick-up of Zircaloy-4 under high pressure up to 10.3MPa are carried out to estimate the pressure effects on the kinetics. Temperature and reaction time are determined to be 37$0^{\circ}C$ and 72hours for the pre-transition test and $700^{\circ}C$ and 210minutes for the post-transition test, respectively. Results show that under 10.3MPa pressure the oxidation reaction is 50% and 100% enhanced in the pre-and the post-transition regime, respectively. Total amount of hydrogen uptake in the reaction is proportionally increased as corrosion weight gain is elevated. However, pick-up fraction is not affected by the high pressure. The fraction is almost twice greater than that in the waterside corrosion. Edges in the specimens play a certain role in the enhancement, especially in the post-transition regime. To identify physical property changes of oxide film such as micro-cracks or micro-pores, careful and thorough examination must be needed with some special techniques.

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References

  1. Atomic Energy Review v.17 The Main Cause of Fuel Element Failure in Water-Cooled Power Reactors F. Garzarolli;R. von Jan;H. Stehle
  2. AECL-4448 Accelerated Oxidation of Zircaloy-2 in Supercritical Steam B. Cox
  3. Proceedings of ANS International Topical Meeting on LWR Fuel Performance High Pressure Steam Corrosion and Hydriding of Zircaloy-4 Y. Ok;S. Kim;Y. Kim;M. Park;D. Min;S. Ro
  4. Fuel for the 90's: ANS / ENS International Topical Meeting on LWR Fuel Performance, Avignon, France v.1 Post-Defect Behavior of Barrier Fuel J.H. Davies;G.A. Potts
  5. EPRI NP-5544 Nuclear Unit Operating Experience S.M. Stroller Corp.
  6. Proc. IAEA Symposium Fuel Element Fabrication with Special Emphasis on Cladding Materials J.N. Chirigos;S. Kass;W.W. Kirk;G.J. Salvaggio
  7. Nucl. Eng. Desg. v.33 Review of Experience with Water Reactor Fuels 1968-1973 D.H. Locke
  8. Proc. 2nd Seminar in Nuclear Materials and Related Technology v.7 no.1 Chemical Processes in Defective Fuel Rods D.R. Olander;W. Wang;Y. Kim;C.Y. Li;S. Lim;S.K. Yagnik
  9. Fuel for the 90's: ANS/ENS International Topical Meeting on LWR Fuel Performance, Avignon, France v.1 Failure of A Barrier Rod in Oskarshamn 3 A. Jonsson;L. Hallstadius;B. Grapengiesser;G. Lysell
  10. ASTM STP 1245 An Experimental Investigation into Oxidation of Zircaloy-4 at Elevated Pressures in 750 to 1000℃ Temperature Range I.L. Bramwell;T.J. Haste;D. Worswick;P.D. Parsons
  11. J. Nucl. Mater. v.82 R.E. Pawel;J.V. Cathcart;J.J. Campbell
  12. EPRI NP-6285-M Evaluation of Fuel Performance at Oconee Unit 2 Babcock & Wilcox
  13. IAEA Atomic Energy Review The Metallurgy of Zirconium (Supplement 1971) D.L. Douglass