ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
The progress so far: An update on the Reactor Pilot Program
It has been about three months since the Department of Energy named 10 companies for its new Reactor Pilot Program, which maps out how the DOE would meet the goal announced by executive order in May of having three reactors achieve criticality by July 4, 2026.
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.