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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
Charles Forsberg
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 63-70
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-137
Articles are hosted by Taylor and Francis Online.
Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation creating a new unexplored dimension in fuel cycle options. This may have large impacts on light water reactor (LWR) closed fuel cycles and waste management. If 240Pu is removed before recycling plutonium as mixed-oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, americium, and curium. Plutonium-240 is a fertile material and thus can be replaced by 238U. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Reducing production of 241Pu by removal of 240Pu reduces production of 241Am—the primary heat generator in spent nuclear fuel after several decades. Reducing heat-generating 241Am would reduce repository size, cost, and waste toxicity. Avoiding 241Am avoids its decay product 237Np, a nuclide that partly controls long-term oxidizing repository performance. The 240Pu could be added to the high-level waste for disposal. Some of these benefits also apply to plutonium recycled into fast reactors. However, the benefits are fewer because in a fast neutron spectrum, 240Pu is both a fissile material and a fertile material. There would be incentives to separate 242Pu and dispose of it as a waste.