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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.
Ralf Wittmaack
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 158-180
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35384
Articles are hosted by Taylor and Francis Online.
New design features of future reactors are being developed to ensure the integrity of the reactors under severe accident conditions. These features include the spreading of corium with subsequent flooding and cooling. Numerical simulations are performed to reduce the number of necessary large-scale experiments with radioactive material. For this reason, the development, verification, and validation of simulation methods are important foci. A method for predicting three-dimensional free-surface flows of a single-component, incompressible Newtonian fluid is presented. The thermodynamics and discrete phase transitions are simulated also. In addition to the fluid, structural materials are considered as hydrodynamic obstacles and heat structures. The method is applied to several flow, heat transfer, and phase transition problems of water and glycerol and of cerrotru (low-melting Bi-Sn alloy), thermite, and corium melts. The predictions provide a satisfactory representation of the experimental data and analytical solutions. Different physical processes are analyzed, e.g., gravity waves, creeping flows, Bénard convection, and thermodynamic interactions of fluid, structural material, and surroundings. The method is applied to the layout and design of experiments and exvessel corium-retention devices in nuclear reactors.