Feasibility of Friction Stir Processing (FSP) as a Method of Healing Cracks in Irradiated 304L Stainless Steels
The current US fleet of nuclear reactors has been in service for three decades. Over this period, existing welds in stainless steel (SS) shrouds have sustained stress corrosion cracking (SCC) and are in need of repair. Additionally, helium has formed interstitially as a byproduct of proton bombardme...
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| Format: | Others |
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BYU ScholarsArchive
2016
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| Online Access: | https://scholarsarchive.byu.edu/etd/6111 https://scholarsarchive.byu.edu/cgi/viewcontent.cgi?article=7111&context=etd |