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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.
Rafael Macian, Peter Cebull, Paul Coddington, Mark Paulsen
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 139-152
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3021
Articles are hosted by Taylor and Francis Online.
RETRAN-3D-MOD002.0 includes a five-equation flow field model to extend the code's analytical capabilities to situations in which thermodynamic nonequilibrium phenomena are important. Evaluation of this model's performance against several depressurization and repressurization transients has shown severe numerical and convergence problems related to the calculation of the interfacial energy and mass transfer. To remove these code limitations, a new interfacial mass and energy transfer model has been developed and implemented in RETRAN-3D. This model calculates the phase change based on the net heat transfer to the liquid-vapor interface at saturation. The heat transfer for each phase is equal to the product of the interfacial area density, a heat transfer coefficient, and the difference between the interface and the bulk temperature of the respective phase. A flow regime map based on the work of Taitel and Dukler is used to identify the flow regime in a control volume and to select the appropriate correlations for these quantities.Assessment of the new model's performance includes the simulation of an experimental depressurization transient, OMEGA test 9; a turbine trip transient in a BWR/4; and a very fast depressurization transient, the Edwards pipe problem. The results are free from the previous numerical problems and show a good agreement with experimental values.