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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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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.
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Language:	English
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description	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.
doi_str_mv	10.1016/0029-5493(85)90070-6
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source	ScienceDirect: Engineering & Technology Backfile; ScienceDirect: Energy & Power Backfiles
title	Sensitization development in austenitic stainless steel piping
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