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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.
Yang-Hyun Koo, Byung-Ho Lee, Jae-Yong Oh, Kun-Woo Song
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 337-347
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A4031
Articles are hosted by Taylor and Francis Online.
Based on the high-burnup fuel data available in open literature, a conservative width of high-burnup structure (HBS) in light water reactor UO2 fuel, which can be used for fuel performance and accident analysis or assessment of spent fuel under geological disposal conditions, is proposed as a function of pellet average burnup. For pellet average burnup of 30 to 60 GWd/t U, where the HBS generally increases with burnup because of the accumulation of irradiation damage, a conservative HBS width is given by wHBS = 13.3 (buavg - 30), where wHBS is the HBS width in m and buavg is the pellet average burnup in GWd/t U. For pellet average burnup of 60 to 75 GWd/t U, where microstructural damage caused by irradiation is partly annealed, a conservative HBS width is expressed by wHBS = 2.02 exp(buavg /11.35). In the case of pellet average burnup above 75 GWd/t U up to at least 100 GWd/t U, the HBS width does not exceed some limiting value of 1.5 mm because high temperature in the central region of the fuel pellet has caused an extensive annealing of irradiation damage. In addition, because of significant fission gas release during irradiation up to high burnup, HBS formation might not have expanded to the pellet region whose temperature was lower than the threshold one. Therefore, for this burnup range, a conservative HBS width is given as wHBS = 1500 m.