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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.
R. K. S. Rathore, P. Munshi, R. K. Jarwal, I. D. Dhariyal
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 227-234
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34109
Articles are hosted by Taylor and Francis Online.
Computerized tomography (CT) has been demonstrated to be a good technique for measuring point density (void fraction) in two-phase flow systems. Recently, improvements have been suggested regarding the choice of filter functions in CT methods. These methods are essentially based on the discrete implementation of the radon inversion formulas that are widely used in the medical imaging area. Such methods do not require any a priori information regarding the distribution of the density (or the void fraction). A very simple method involving the tomographic chord-segment inversion has been developed and tested for two-phase flows having radially symmetric density distributions. This method is much simpler and consumes less CPU time than more general methods of tomographic reconstruction. For test functions, the reconstructed density distributions are almost exact. For air/water bubbly flow data, the reconstructed values have a maximum deviation of ±0.03 g/cm3. The range of investigation of the air/water flow data was 0.6 to 0.9 g/cm3, i.e., a void fraction range of 40 to 10%. These results are comparable to the results obtained by the more general methods based on the radon inversion formulas.