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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.
Günter Fieg, Manfred Möschke, Heinrich Werle
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 309-317
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34715
Articles are hosted by Taylor and Francis Online.
The potential for recriticalities and high energetics during the transition phase of a hypothetical coredisruptive accident in a liquid-metal fast breeder reactor is strongly dependent on the fissile fuel inventory remaining in the core region. To investigate the ability of the fuel to penetrate unblocked flow paths, a series of experiments with pin bundle geometry has been performed at the THEFIS facility using alumina and alumina-iron melts as fuel simulants. Several series of similar experiments were done previously with tubes, annuli, and three-pin bundles using alumina, iron, and mixtures of alumina and iron melts. In this new series, seven-pin bundles with wire wrappers and grid spacers defining the cooling channels between the single pins have been investigated. These bundles are a more realistic representation of the upper blanket structure. These out-of-pile experiments have been analyzed with the PLUGM code, which is based on the assumption of stable crust growth during the penetration and freezing process. The differences in results between out-ofpile experiments using alumina and those using UO2 are discussed, and an explanation for these discrepancies is indicated.