Nuclear Engineering and Technology

  • 제35권5호
  • /
  • Pages.378-386
  • /
  • 2003
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

Hydriding Failure Analysis Based on PIE Data

  • 발행 : 2003.10.01
⟨ 이전 논문 다음 논문 ⟩

초록

Recently failures of nuclear fuel rods in Korean nuclear power plants were reported and their failure causes have been investigated by using PIE techniques. Destructive and physico-chemical examinations reveal that the clad hydriding phenomena had caused the rod failures primarily and secondarily in each case. In this study, the basic mechanisms of the primary and the secondary hydriding failures are reviewed, PIE data such as cladding inner and outer surface oxide thickness and the restructuring of the fuel pellets are analyzed, and they are compared with the predicted behaviors by a fuel performance code. In addition, post-defected fuel behaviors are reviewed and qualitatively analyzed. The results strongly support that the hydriding processes, primary and secondary, played critical roles in the respective fuel rods failures and the secondary hydriding failure can take place even in the fuel rod with low linear heat generation rate.

키워드

참고문헌

  1. F. Garzarolli, R. von Jan, and H. Stehle, The Main Cause of Fuel Element Failure in Water-Cooled Power Reactors, Atomic Energy Review, 17 (1979) 31
  2. S.M. Stoller Co., Nuclear Unit Operating Experience, EPRI NP-5544 (1987)
  3. D.H. Locke, Review of Experience with Water Reactor Fuels in 1968-1973, Nucl. Eng. Desg., 33 (1975) 94 https://doi.org/10.1016/0029-5493(75)90017-5
  4. S. Vaknin and D.R. Olander, Secondary Hydriding of Defected Zircaloy-Clad Fuel Rods, EPRI RP-1250-23 (1972)
  5. J.C. Clayton, Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods, Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023 (1989) 266
  6. Combustion Engr. Inc., ESCORE-the EPRI Steady State Core Reload Evaluator Code, EPRI NP-5100 (1987)
  7. KAERI and ABB/CE, Nuclear Design Report for Yonggwang Unit 4 Cycle 1, Rev. 0 (1995)
  8. A. Jonsson, L. Hallstadius, B. Grapengiesser, and G. Lysell, Failure of A Barrier Rod in Oskarshamn 3, Fuel for the '90's: Proc. ANS/ENS International Topical Meeting on LWR Fuel Performance, Avignon, France, Vol. 1 (April 1991) 371
  9. J.H. Davies and G.A. Potts, Post-defect Behavior of Barrier Fuel, Fuel for the 90's: Proc. ANS/ENS International Topical Meeting on LWR Fuel Performance, Avignon, France, Vol. 1 (April 1991) 272
  10. A.M. Garde, Enhancement of Aqueous Corrosion of Zircaloy-4 Due To Hydride Precipitation at the Metal-Oxide Interface, Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132 (1991) 564
  11. M. Blat and D. Noel, Detrimental Role of Hydrogen on the Corrosion Rate of Zirconium Alloys, Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295 (1996) 319
  12. S. Kim and Y. Kim, Oxidation vs. Hydriding of Zircaloy-4, J. Nucl. Mater. (to be published)
  13. B.J. Lewis, F.C. Inglesias, D.S. Cox, and E. Gheorghiu, Nucl. Technol. 92 (1990) 353
  14. H. Stehle, H. Assmann, and F. Wunderlich, Uranium Oxide Properties For LWR Fuel Rods, Nucl. Eng. Desg., 33 (1975) 230 https://doi.org/10.1016/0029-5493(75)90024-2
  15. P.G. Lucuta, Hj Matzke, and R.A. Verrall, J. Nucl. Mater., 223 (1995) 51 https://doi.org/10.1016/0022-3115(94)00703-9
  16. M. Amaya, T. Kubo, and Y. Korei, J. Nucl. Sci. Technol. 33 (1996) 636
  17. Amato, R.L. Colombo, and A.M. Protti, J. Amer. Ceram. Soc., 46 (1963) 407
  18. H. Assmann, W. Dorr, and M. Peehs, Control of $UO_2$ Microstructure By Oxidative Sintering, J. Nucl. Mater., 140 (1986) 1 https://doi.org/10.1016/0022-3115(86)90189-3