Thermodynamic and Experimental Study of Sodium Hydroxide Decomposition in Sodium between 430 and 550 °C

  • Claude Oberlin
  • Pierre Saint-Paul


Earlier tests (1) carried out in sodium polluted (up to 10%) by sodium hydroxide between 400 and 550 °C have shown that the austenitic materials used (especially Alloy 800) for the steam generator tubes of fast breeder reactors cooled with sodium could induce a risk of stress corrosion cracking in this medium. However, in sodium polluted by sodium oxide, the same materials are not affected by this phenomenon in the same conditions of stress, but are only subject to slight intergranular corrosion.


Sodium Hydroxide Stress Corrosion Hydrogen Pressure Steam Generator Partial Hydrogen Pressure 
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  1. 1.
    P. Berge, C. Oberlin, P. Saint-Paul, M. Zbinden, J. of Nuclear Materials, 66, 65 (1977).CrossRefGoogle Scholar
  2. 2.
    EDF, DER, Internal report (1980).Google Scholar
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    J. L. Henry, S. A. O’Hare, M. P. Krug, USBM, 1532, (1971).Google Scholar
  4. 4.
    J. P. Maupré, Report CEA, R 4905 (1978).Google Scholar

Copyright information

© Plenum Press, New York 1982

Authors and Affiliations

  • Claude Oberlin
    • 1
  • Pierre Saint-Paul
    • 1
  1. 1.Electricité de FranceEcuellesFrance

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