A Study of the Effect of Oxidation on the Mechanical Properties of Zircaloy-4

Zircaloy-4에서 산화가 기계적 성질에 미치는 영향에 대한 연구

  • 고진현 (한국기술교육대학교 신소재공학과) ;
  • 김상호 (한국기술교육대학교 신소재공학과) ;
  • 황용화 (한국원자력연구소)
  • Published : 2002.10.01

Abstract

A study on the change of mechanical properties and oxidation behavior of Zircaloy-4 fuel cladding after exposing at 90$0^{\circ}C$ and $1000^{\circ}C$ for various periods of exposure time under the steam atmosphere was carried out. The growth of the $ZrO_2$ layer combined with an oxygen-rich-phase layer into the Zircaloy tube material can be described by an expression, E = 1.1√Dt + $2 $\times$ 10^{-4}$ . The tensile strength of Zircaloy tubes increased for a short period of exposure time and decreased rapidly with further exposure while the hoop strength was not decreased greatly. In the meantime, the axial and circumferential elongations of oxidized Zircaloy tubes were decreased drastically with increasing exposure time as a result of embrittlement phenomena.

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References

  1. S. Banerjee and W. Hankox : Private Communication (1990)
  2. R. W. Griebe and J. O. Zance: (BWR-FLE-CHET) IN-1385 (1970) 327
  3. R. S. Shumay and J. O. Zane : (PWR-FLE-CHT) IN-1386 (1970) 548
  4. C. M. Moser and R. W. Griebe : (PWR-FLE-CHT) IN-1355 (1970) 109
  5. R. J. Jensen : (FHUST) IN-1398, (1970) 785
  6. E. Kohn : AECL-EC (1981) 29
  7. H. M. Chung and T. F. Kassner : ANL-77-31 (1978) 115
  8. H. M. Chung and T. F. Kassner : ANL-79-48 (1980) 39
  9. D. G. Hardy : CRNL-2494-3 (1983) 28
  10. K. P. Steward and B. A. Cheadle : AECL-2627 (1966) 17
  11. ASTM B 353-71 : Standard Specification for Wrought Zirconium and Zirconium Alloys Seamless and Welded Tubes for Nuclear Service (1973)
  12. M. J. Garber and W. F. Zelezny : Trans. Am Nucl. Soc. 23 (1969) 358
  13. F. H. Krenz : AECL-1313 (1972) 13
  14. A. W. Leimmon : ASTM STP 633 ( 1976) 211
  15. T. Furata, H. Uetsuka and S. Kawasaki :ASTM STP 824 (1984) 734