Zobrazeno 1 - 4
of 4
pro vyhledávání: '"Yongkyun Yu"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4060-4066 (2021)
Flow-accelerated corrosion (FAC) of carbon steel piping is a significant problem in nuclear power plants. The basic process of FAC is currently understood relatively well; however, the accuracy of prediction models of the wall-thinning rate under an
Externí odkaz:
https://doaj.org/article/fa49902b8ee7438c9554ab7ccacc6846
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 4, Pp 1199-1209 (2021)
The detection of unexpected loose parts in the primary coolant system in a nuclear power plant remains an extremely important issue. It is essential to develop a methodology for the localization and mass estimation of loose parts owing to the high pr
Externí odkaz:
https://doaj.org/article/b506e06930e64e98a50eae6b1c28e693
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4060-4066 (2021)
Flow-accelerated corrosion (FAC) of carbon steel piping is a significant problem in nuclear power plants. The basic process of FAC is currently understood relatively well; however, the accuracy of prediction models of the wall-thinning rate under an
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 4, Pp 1199-1209 (2021)
The detection of unexpected loose parts in the primary coolant system in a nuclear power plant remains an extremely important issue. It is essential to develop a methodology for the localization and mass estimation of loose parts owing to the high pr