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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.
Rahim Nabbi, Wilfried Jahn, Gerhard Meister, Werner Rehm
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 172-189
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33216
Articles are hosted by Taylor and Francis Online.
Analysis of extreme water ingress accidents in the pebble bed high-temperature reactor of 500-MW(thermal) power during the first few minutes shows that the temperature coefficients of reactivity limit the power increase, presupposing no action of the shutdown system and other safety devices. The rupture of all steam generator tubes with the highest ingress rate of 55 kg/s results in a power maximum of 1.8 times the initial value after ∼1 min. The system pressure increases from the operating value of 40 bar up to the design value of 50 bar. Fuel temperatures do not reach values that cause fuel particle damage and fission product release. Hence, special requirements on the promptness of shutdown rod actions are not needed to limit accident consequences in the core. Overpressurization of the reactor vessel will arise, however, if water ingress with the highest rate continues. Water ingress at a small rate (7 kg/s), corresponding to the rupture of a few tubes, results in a rather slow power increase up to 1.3 times the initial value and to a primary system pressure of 43 bar after 5 min.