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Growth beyond megawatts
Hash Hashemianpresident@ans.org
When talking about growth in the nuclear sector, there can be a somewhat myopic focus on increasing capacity from year to year. Certainly, we all feel a degree of excitement when new projects are announced, and such announcements are undoubtedly a reflection of growth in the field, but it’s important to keep in mind that growth in nuclear has many metrics and takes many forms.
Nuclear growth—beyond megawatts—also takes the form of increasing international engagement. That engagement looks like newcomer countries building their nuclear sectors for the first time. It also looks like countries with established nuclear sectors deepening their connections and collaborations. This is one of the reasons I have been focused throughout my presidency on bringing more international members and organizations into the fold of the American Nuclear Society.
Alejandra de Lara, Zsolt Soti, Arndt Schubert, Paul van Uffelen, Eugene Shwageraus
Nuclear Science and Engineering | Volume 199 | Number 12 | December 2025 | Pages 2018-2036
Research Article | doi.org/10.1080/00295639.2025.2525035
Articles are hosted by Taylor and Francis Online.
This paper presents an efficient computational approach for modeling the propagation of uncertainties in input variables to output variables in fuel rod thermal-mechanical simulations. Our primary goal was to develop a methodology to identify a reduced sample size capable of providing information on uncertainties and sensitivities while remaining cost effective for computation-intensive high-fidelity three-dimensional simulations or full-core calculations.
Our method uses the best-estimate code TRANSURANUS (TU), which is equipped with a built-in Monte Carlo engine. This framework allows for the introduction of uncertainties into the selected input parameters through minor modifications in the input file used for the reference case. We applied this methodology to analyze a representative fuel rod proposed for use in the conceptual molten-salt fluoride-cooled high-temperature reactor (FHR), adapted to the geometry of the advanced gas-cooled reactor (AGR).
The computational efficiency of our approach lies in the reduced number of input/output operations. Consequently, we can execute numerous TU runs, enabling a comprehensive comparison of the results generated with a smaller number of statistical runs. To support statistical postprocessing, we developed the TUPython tool. With this tool, we can quantitatively assess both temporal and spatial variations as well as the sensitivity of fuel behavior model responses. The study showed that the sample size of 153, defined by the fourth-order Wilks’ method, can be used to economically model uncertainty propagation and perform sensitivity analyses in this specific case.