The oxidation of alloy 690 in simulated pressurized water reactor primary water

Kuang, Wenjun / Song, Miao / Wang, Peng et al. | British Library Online Contents | 2017

Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690

Xia, Xiao-feng / Lü, Zhan-peng / Chen, Jun-jie | British Library Online Contents | 2015

Stress Corrosion Cracking Growth of Alloy 800NG in Pressurized Water Reactor Primary Water

Arioka, Koji / Staehle, Roger W. / Tapping, Robert L. et al. | British Library Online Contents | 2018

Stress corrosion crack initiation in machined type 316L austenitic stainless steel in simulated pressurized water reactor primary water

Chang, Litao / Burke, M. Grace / Scenini, Fabio | British Library Online Contents | 2018

The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water

Yamazaki, S. / Lu, Z. / Ito, Y. et al. | British Library Online Contents | 2008