Behavior of stainless steels in pressurized water reactor primary circuits

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Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water

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Impact of localized deformation on IASCC in austenitic stainless steels

Zhijie Jiao, Gary S. Was · Journal of Nuclear Materials · 2010 · 126 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +13

Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part II: Irradiation induced hardening

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IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions

Hiromasa Nishioka, Koji Fukuya, Katsuhiko Fujii et al. · Journal of Nuclear Science and Technology · 2008 · 45 citations

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