Zobrazeno 1 - 10
of 51
pro vyhledávání: '"Jibo Tan"'
Publikováno v:
Corrosion Communications, Vol 6, Iss , Pp 52-61 (2022)
The optimization of water chemistry in pressurized water reactor (PWR) primary circuit is one of the most effective ways to achieve both safety and economy for operating PWR nuclear power plants (NPPs). Special attention has been paid to fundamental
Externí odkaz:
https://doaj.org/article/587f5c80d6cf46719c29822894ad581b
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2977-2981 (2021)
Corrosion fatigue crack growth (FCG) behavior of 316LN stainless steel was investigated in high-temperature pressurized water at different temperatures, load ratios (R = Kmax/Kmin) and rise times (tR). The environmental assisted effect on FCG rate wa
Externí odkaz:
https://doaj.org/article/340b9dd1e38647ddb56396166500fd7e
Autor:
Jun Gao, Chang Liu, Jibo Tan, Ziyu Zhang, Xinqiang Wu, En-Hou Han, Rui Shen, Bingxi Wang, Wei Ke
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2600-2609 (2021)
Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, high-temperature air and in light water reactor (LWR) water environments. The fatigue mean curve and design curve for the low-alloy steel are developed
Externí odkaz:
https://doaj.org/article/9c55b1bf580446909cfcfef102827109
Publikováno v:
Materials, Vol 15, Iss 15, p 5434 (2022)
Crevice corrosion behavior of Alloy 690 in high-temperature aerated chloride solution was studied using a self-designed crevice device. The SEM, EDS, XRD, and XPS analyses results indicated that the oxide films outside the crevice consisted of Ni-Cr
Externí odkaz:
https://doaj.org/article/ce408c6922ce45d28a88cc4d34c6097e
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2977-2981 (2021)
Corrosion fatigue crack growth (FCG) behavior of 316LN stainless steel was investigated in high-temperature pressurized water at different temperatures, load ratios (R = Kmax/Kmin) and rise times (tR). The environmental assisted effect on FCG rate wa
Autor:
Rui Shen, Jibo Tan, Jun Gao, Ziyu Zhang, Wei Ke, En-Hou Han, Xinqiang Wu, Bingxi Wang, Chang Liu
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2600-2609 (2021)
Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, high-temperature air and in light water reactor (LWR) water environments. The fatigue mean curve and design curve for the low-alloy steel are developed
Autor:
Ziyu Zhang, Wang Xiang, Fangqiang Ning, Ying Yang, Dan Jia, Jibo Tan, En-Hou Han, Xinqiang Wu
Publikováno v:
Journal of Materials Science & Technology. 70:136-144
The uniform corrosion behavior of model FeCrAl alloys as well as commercial Zircaloy-4 as reference material were investigated in 360 °C borated and lithiated water. The results reveal that FeCrAl alloys exhibited better corrosion resistance than Zi
Publikováno v:
Journal of Materials Science & Technology. 66:163-176
The crevice corrosion behavior of Alloy 690 was investigated in high-temperature chloride solution containing different concentrations of thiosulfate (S2O32-) and dissolved oxygen (DO). The S2O32- inhibited corrosion of Alloy 690 through consuming ox
Publikováno v:
Corrosion Science. 215:111052
Publikováno v:
Journal of Nuclear Materials. 575:154226