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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.
Tetsuya Mouri, Shigeo Ohki
Nuclear Technology | Volume 212 | Number 2 | February 2026 | Pages 490-509
Regular Research Article | doi.org/10.1080/00295450.2025.2472530
Articles are hosted by Taylor and Francis Online.
This study investigates the characteristics of the Doppler coefficient and sodium void reactivity of a burning fast reactor core concept that was constructed in a previous study. This concept allows for multiple recyclings of plutonium and minor actinides [transuranium (TRU)]. TRU degradation due to multiple recycling deteriorates the reactivity coefficients through indirect effects, such as by hardening the neutron spectrum and steepening the energy gradient of neutron importance.
Using silicon-carbide (SiC) structural material improves the reactivity coefficient by causing an opposite indirect effect of TRU degradation. This improvement results not only from neutron spectrum softening due to the neutron moderation effect from 12C but also from the neutron leakage effect resulting from the low structural material density. The disadvantage of increased calculation uncertainty from using SiC structural material can be practically ignored.
Furthermore, the burning core has Doppler coefficient enhancement characteristics from the moderated neutron reflection effect from outside the core. This characteristic has the potential to provide a new measure for reactivity coefficient deterioration due to TRU degradation. The reactivity coefficient characteristics clarified in this study can provide valuable knowledge for future detailed designs and design improvements of a TRU burning core.