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Analysis of residual stresses in girth welded type 304 stainless steel pipes. [BWR type reactors]

Journal Article · · J. Mater. Energy Syst.; (United States)
DOI:https://doi.org/10.1007/BF02833321· OSTI ID:6675458
Intergranular stress corrosion cracking (IGSCC) in boiling water reactor (BWR) piping is a problem for the nuclear power industry. Tensile residual stresses induced by welding are an important factor in IGSCC of Type 304 stainless steel pipes. Backlay and heat sink welding can retard IGSCC. 17 refs.
Research Organization:
Battelle, Columbus Lab, Ohio, USA
OSTI ID:
6675458
Journal Information:
J. Mater. Energy Syst.; (United States), Journal Name: J. Mater. Energy Syst.; (United States) Vol. 3:3; ISSN JMSMD
Country of Publication:
United States
Language:
English