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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.
Hermann Würz
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 193-206
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34556
Articles are hosted by Taylor and Francis Online.
A method for nondestructive assay of spent light water reactor fuel assemblies based on a combination of active and passive neutron counting is presented. After geometrical optimization, the Fuel Assembly Monitoring System (FAMOS) is a rather simple system. It allows the burnup, initial enrichment, type of fuel (uranium or mixed oxide), and criticality of the spent-fuel assembly to be determined. The results of a characterization program with emphasis on boiling water reactor (BWR) fuel assemblies are discussed. Burnup-dependent neutron emission data for spent BWR fuel are now available. The effect of steam void on plutonium and curium buildup is demonstrated. Because of this effect, the axial measurement position is of importance for an accurate assay. If the measurement is done at the upper part of the BWR fuel assembly, the error in burnup remains below ±2 GWd/tonne U, and the initial enrichment can be determined with an accuracy of ±15%. This still allows a clear distinction between the different enrichment regions used for BWR fuel assemblies.