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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.
André Puill, Jean Bergeron
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 123-140
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35381
Articles are hosted by Taylor and Francis Online.
An objective is to enhance the use of plutonium in conventional or slightly modified pressurized water reactors, while minimizing minor actinide production. Having entirely mixed-oxide-fueled reactors reduces the number of reactors that are affected on plutonium recycling and avoids the need for fuel zoning. However, the overall consumption is <30%, and the mass of minor actinides produced is considerable, representing up to 25 % of the plutonium used. The Advanced Plutonium Fuel Assembly concept, based on a uranium-free plutonium fuel, which achieves high burnups and an increased moderation ratio, enables 60% of the second-generation plutonium to be consumed, while the minor actinides produced only represent 8% of this figure. The heterogeneous design of the fuel assembly, which includes natural uranium or low-enriched uranium fuel rods, guarantees values that suit the physical parameters of the core. The concept was analyzed from a thermo-hydraulic aspect in both rated and accident situations. Technological feasibility is yet to be demonstrated. This study is part of a medium-term strategy for the back end of the fuel cycle.