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Fusion Science and Technology
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Getting back to yes: A local perspective on decommissioning, restart, and responsibility
For 45 years, Duane Arnold Energy Center operated in Linn County, Ia., near the town of Palo and just northwest of Cedar Rapids. The facility, owned by NextEra Energy, was the only nuclear power plant in the state.
In August 2020, a historic derecho swept across eastern Iowa with winds approaching 140 miles per hour. Damage to the plant’s cooling towers accelerated a shutdown that had already been planned, and the facility entered decommissioning soon after, with its fuel removed in October of that year. Iowa’s only nuclear plant had gone off line.
Today the national energy landscape looks very different than it did just six short years ago. Electricity demand is rising rapidly as data centers, artificial intelligence infrastructure, advanced manufacturing, and electrification expand across the country. Reliable, carbon-free baseload power has become increasingly valuable. In that context, Linn County has approved the rezoning necessary to support the recommissioning and restart of Duane Arnold and is actively supporting NextEra’s efforts to secure the remaining state and federal approvals.
A. C. Uggenti, G. F. Nallo, A. Carpignano, N. Pedroni, R. Zanino
Fusion Science and Technology | Volume 78 | Number 3 | April 2022 | Pages 186-198
Technical Paper | doi.org/10.1080/15361055.2021.1984720
Articles are hosted by Taylor and Francis Online.
A preliminary but systematic safety analysis of a liquid metal divertor (LMD) for the EU DEMO performed by means of the Functional Failure Mode and Effect Analysis (FFMEA) is presented. This methodology is suitable for the analysis of the LMD, which is undergoing preconceptual design. In fact, the FFMEA compensates for the lack of detailed design information by postulating the loss of a system function, rather than a specific component failure.
The implementation of the FFMEA led to a better understanding of the safety and operational issues associated with the system and to the identification of a list of postulated initiating events (PIEs), i.e., the most challenging conditions for the plant. The PIEs, together with their possible consequences, represent an input for future quantitative safety analyses. Due to the early design stage of the LMD and the iterative nature of the methodology, this list will evolve alongside the design detail and with improvements in the understanding of phenomena driving reactor behavior.
The study highlighted some safety-relevant issues, e.g., those related to materials compatibility and system modularity, to be addressed in the perspective of a safety-driven design evolution.