Author:
Zhao Peng,Zhang Pan,Wang Ning,Yu Hao,Gong Jian-guo,Xuan Fu-zhen
Reference60 articles.
1. Crack growth and cracking beha vior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary wat er;Y S Lim;Nuclear Engineering and Technology,2019
2. Effect of a heat trea tment on the precipitation behavior and tensile properties of alloy 690 steam ge nerator tubes;T.-H Lee;Journal of Nuclear Materials,2016
3. Effect of grain size on mechanical property and corrosion resistance of the Ni-based alloy 690;J Lv;Journal of Materials Science & Technology,2018
4. Low cycle fatigue behavior of alloy aterials;J.-D Hong;Science and Engineering: A,2014
5. Tensile Behavior of Alloy 690 in the Dynamic Stra in Aging Regime;K Sourabh;J. of Materi Eng and Perform,2022