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Academic Articles
(Invited Paper) Vol.1 (2009) p.1 - p.29
 
Stress Corrosion Cracking in Low Carbon Stainless Steel Components in BWRs
 
Shunichi SUZUKI1, Kenrou TAKAMORI1, Katsuhiko KUMAGAI1, Akihiro SAKASHITA2, Norimichi YAMASHITA2, Chikashi SHITARA3 and Yuichi OKAMURA4
 
1 Materials Engineering Center, Tokyo Electric Power Company (TEPCO), 4-1 Egasaki-cho, Tsurumi-ku, Yokohama 230-8510, Japan
2 Nuclear Asset Management Dept., TEPCO, 1-1-3 Uchisaiwai-cho, Chiyoda-ku, Tokyo 101-0001, Japan
3 Nuclear Quality & Safety Management. Dept.,TEPCO, 1-1-3 Uchisaiwai-cho, Chiyoda-ku, Tokyo 101-0001, Japan
4 Fukushima-dai2 Nuclear Power Station, TEPCO, 12 Kobamasaku, Namikura, Naraha-machi, Futaba-gun, Fukushima 979-0695, Japan
 
Abstract
In recent years, numbers of SCC have occurred in core shrouds and primary loop recirculation piping made of low carbon stainless steels that had been recognized to be an SCC-resistant material. These incidents resulted in long-term shutdown of Japanese boiling water reactors and have drawn social as well as technical interests. This paper will provide an introductory review on (1) background of SCC observed in low carbon stainless steel components in BWRs, (2) characteristics of SCC in core shrouds and PLR piping, (3) structural integrity evaluation, (4) SCC mitigation techniques, (5) SCC mechanism and (6) research topics that should be covered regarding these issues.
 
Keywords
stress corrosion cracking, low carbon stainless steel, L-grade, BWR, core shroud, recirculation piping, PLR, BWR
 
Full Text: PDF
 
(Received: January 9th, 2009)