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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.
J. Mazeika, R. Petrosius, V. Jakimaviciute-Maseliene, D. Baltrunas, K. Mazeika, V. Remeikis, T. Sullivan
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 156-168
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT08-A3920
Articles are hosted by Taylor and Francis Online.
The paper presents the long-term safety assessment of the Maisiagala radioactive waste repository (Lithuania) using the advanced computer codes DUST, FEFLOW, and AMBER. The software DUST was employed for calculations of the one-dimensional leaching flux of radionuclides from the repository vault and subsequent transport in the unsaturated zone. Using the mass flux of radionuclides calculated in DUST as a source to the aquifer, the software FEFLOW was used for two-dimensional assessment of activity concentrations of radionuclides in groundwater. Using the groundwater concentrations calculated in FEFLOW, the code AMBER was used to calculate the dose over time at four hypothetical wells downstream from the repository. The well distances ranged from 150 to 1600 m.When the hypothetical drinking water well is installed 150 m from the repository (close to the outside perimeter of the controlled area), the highest effective doses will arise from 3H, 36Cl, and 239Pu. The doses determined by 3H and 36Cl may exceed a dose limit of 1 mSv/yr for 50 to 230 yr after the closure of the facility (1989). The dose of 239Pu will remain almost constant for >60 000 yr after the closure, yet it will not exceed the dose limit value. According to previous studies, the intrusion scenario is much more critical compared to the groundwater exposure pathway in the case of 239Pu (as well as 226Ra).