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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
Jae Jun Jeong, Tae Gang Lee, Sang Gyun Nam, Byongjo Yun
Nuclear Technology | Volume 211 | Number 8 | August 2025 | Pages 1875-1882
Note | doi.org/10.1080/00295450.2024.2428553
Articles are hosted by Taylor and Francis Online.
The flow in a helically coiled tube exhibits a unique characteristic due to the centrifugal force acting on the fluid, which generates a secondary flow perpendicular to the main axial flow. This phenomenon is known to enhance convective heat transfer in both single- and two-phase flows. To account for this effect in a boiling heat transfer correlation, a new dimensionless number, defined by the ratio of centrifugal force to gravitational force, was introduced in a previous study. That study suggested a correlation incorporating this dimensionless number.
This work aims to improve on the previous correlation. In deriving the dimensionless centrifugal force number, the pitch of the helical tube was not considered in the previous work. By properly incorporating both pitch and helical diameter into the dimensionless number, the coefficients of the heat transfer correlation must also be adjusted. The modified correlation was evaluated using 617 steam-water experimental data points for boiling heat transfer in helically coiled tubes. The results indicate that the modified correlation shows better results in comparison with the previous one and other existing correlations in terms of the root-mean-square errors of the calculated heat transfer coefficients.