Sensitization development in austenitic stainless steel piping

Pacific Northwest Laboratory and the Division of Engineering Technology of the US Nuclear Regulatory Commission are conducting a program to determine a method for evaluating welded and repair-welded stainless steel piping for light-water reactor service. Validated models, based on experimental data,...

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Bibliographic Details
Published in:Nuclear engineering and design 1985-11, Vol.89 (2), p.319-331
Main Authors: Bruemmer, S.M., Page, R.E., Atteridge, D.G.
Format: Article
Language:English
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Summary:Pacific Northwest Laboratory and the Division of Engineering Technology of the US Nuclear Regulatory Commission are conducting a program to determine a method for evaluating welded and repair-welded stainless steel piping for light-water reactor service. Validated models, based on experimental data, are being developed to predict the degree of sensitization (DOS) and the intergranular stress corrosion cracking (IGSCC) susceptibility in the heat-affected zone (HAZ) of the SS weldments. The cumulative effects of material composition, past fabrication procedures, past service exposure, weldment thermomechanical (TM) history, and projected post-repair component life are being considered.
ISSN:0029-5493
1872-759X
DOI:10.1016/0029-5493(85)90070-6