Author:
Lim Yun Soo,Kim Dong Jin,Kim Sung Woo,Hwang Seong Sik,Kim Hong Pyo
Funder
Korean Nuclear R&D Program
Korea Atomic Energy Research Institute
Subject
Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science
Reference46 articles.
1. A review of Alloy 600 cracking in operating nuclear plants: Historical experience and future trends;Bamford,2003
2. Crack growth response of Alloy 690 in simulated PWR primary water;Toloczko,2009
3. Crack growth rates for evaluating PWSCC of thick-wall Alloy 600 material;White,2003
4. Study of grain boundary character along intergranular stress corrosion crack paths in austenitic alloys;Gertsman;Acta Mater.,2001
5. Microstructural characterization on intergranular stress corrosion cracking of Alloy 600 in PWR primary water environment;Lim;J. Nucl. Mater.,2013
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