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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
Integrating Waste Management for Advanced Reactors: The Universal Canister System and Project UPWARDS
When the Department of Energy’s Advanced Research Projects Agency–Energy launched the Optimizing Nuclear Waste and Advanced Reactor Disposal Systems (ONWARDS) program in 2022, it posed a challenge that the nuclear industry had never seriously confronted before: how to design waste management solutions that anticipate the coming shift to advanced reactors and not merely retrofit existing systems built for an older generation of technology. The program’s objectives were ambitious—reduce disposal footprint, enable scalable pathways for unfamiliar waste streams, and build the technical foundations for future disposal—yet also tightly grounded in the realities of emerging nuclear fuel cycles. For the nuclear community, this was a timely call. Advanced reactors were accelerating toward deployment, but the waste management systems needed to support them had not kept pace.
George M. Jacobsen, Chris Ellis, Joel Kosmatka, Herbert Shatoff, Panto Mijatovic, Ricardo Lebensohn, Laurent Capolungo, Kevin Spilker, Kyle Gamble, Gyanender Singh, Jason Hales, Christina A. Back
Nuclear Technology | Volume 212 | Number 1 | January 2026 | Pages 1-19
Research Article | doi.org/10.1080/00295450.2025.2480978
Articles are hosted by Taylor and Francis Online.
The accelerated fuel qualification (AFQ) framework has been used for the initial development of multiscale modeling of silicon carbide (SiC) fiber reinforced composite (SiC-SiC). The AFQ framework provides a methodology to leverage physics-informed multiscale modeling along with a reduced set of empirical test data to reduce the time and cost of licensing and qualification of new nuclear fuel systems while maintaining the overall nuclear power plant safety case. SiC-SiC is being proposed for in-core applications, most notably fuel cladding, for current and next-generation nuclear reactors because of its high temperature stability, irradiation tolerance, and ability to withstand many accident conditions. As these composites exhibit multiscale architectures and complex microstructure-based fracture mechanics, it is an appealing use case for the AFQ methodology. While the end goal of this work is a single multiscale model that can be used for predictive in-core performance, current focus is on the individual various length scale models. Four individual models have been initially developed from microscale to engineering system level to capture key physics-based effects across different length scales. These models include a microscale homogenized tow model, a mesoscale fast Fourier transform–based weave model that integrates the homogenized tow model, a mesoscale finite element–based weave model, and a system-level BISON fuel performance model. Results of these models have undergone an initial comparison with separate-effects test data showing a good match to experimental results. By using the AFQ framework during model development, several near-term benefits have been secured including a reduction in development time for the SiC-SiC cladding, more targeted irradiation testing, and a better understanding of uncertainty.