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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.
Su-Jong Yoon, Chang-Yong Jin, Min-Hwan Kim, Goon-Cherl Park
Nuclear Technology | Volume 175 | Number 2 | August 2011 | Pages 419-434
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT11-A12313
Articles are hosted by Taylor and Francis Online.
An accurate prediction of core bypass flow is of great importance in the design of very high temperature reactor (VHTR) cores in terms of the fuel thermal margin and safety. In the present study, a unit-cell experiment and computational fluid dynamics (CFD) analysis were carried out to evaluate the amount and distribution of core bypass flow. This study examined the effects of the inlet mass flow rate, block combinations, and thickness of the bypass gap. The prediction capability of the CFD code FLUENT was validated by the unit-cell experimental result. The analysis was extended to the entire core region. In this simulation, a quarter core was simulated using the nonconformal grid method to reduce the computational cost and time. The accuracy and applicability of the nonconformal grid method were assessed from the experimental results and comparative simulation. In conclusion, the flow distribution in the VHTR core was evaluated by the CFD core model with low error and computational cost.