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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.
Hatice Akkurt, Naeem M. Abdurrahman
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 301-314
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A3003
Articles are hosted by Taylor and Francis Online.
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Center under the joint sponsorship of the Empire State Atomic Development Associates (ESADA) and Westinghouse using mixed-oxide (MOX) fuel. During the experimental program, both single- and multiregion critical core configurations were constructed for different fuel types and lattice pitches. Two types of MOX fuels and a low-enriched UO2 fuel were used. A description of selected single-region ESADA experiments with criticality benchmark calculation results for those experiments as well as sensitivity analysis results on some configurations is given. Criticality calculations were performed using MCNP-4A with both ENDF/B-V and ENDF-B/VI cross-section libraries. The calculational results show that the calculated eigenvalues with ENDF/B-V cross-section libraries are higher than calculated eigenvalues with ENDF/B-VI cross-section libraries for all types of fuel. Calculational results also indicate that there is an increase in keff with increasing lattice pitch with both cross-section libraries. The uncertainties in keff value due to some uncertainties in the measured data are also calculated.