Corrosion Product Release into Sodium from Austenitic Stainless Steel

  • William F. Brehm
  • R. P. Anantatmula


During operation of a sodium-cooled nuclear reactor, the fuel cladding and in-core materials will undergo material loss (corrosion) by the flowing sodium. An experimental program to characterize the release and transport of corrosion products has been active at our laboratory since 1966. The purpose of this paper is to describe the results of radioactive and non-radioactive corrosion product release from austenitic stainless steel obtained during the study and to identify some release mechanisms. The previous excellent reviews of material corrosion in sodium (1, 2) did not discuss release of manganese and cobalt, the two most significant radioactive species. Discussion of control measures against radioactive material transport, and general summaries of that problem have also been presented elsewhere (3, 4, 5).


Austenitic Stainless Steel Diffusion Profile 60Co Release Weight Loss Data Ferrite Layer 
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Copyright information

© Plenum Press, New York 1982

Authors and Affiliations

  • William F. Brehm
    • 1
  • R. P. Anantatmula
    • 1
  1. 1.Hanford Engineering Development LaboratoryRichlandUSA

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