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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
Alireza Haghighat, Maurice A. Robkin
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 503-513
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33175
Articles are hosted by Taylor and Francis Online.
The long-term reduction in potential hazard of geologically stored nuclear wastes achievable by partitioning and transmutation (PT) of the actinides discharged from a mixed-oxide (MOX)-fueled light water reactor coupled to a MOX-fueled liquid-metal fast breeder reactor (LMFBR) is considered for three PT cases:1. 32 cycles of PT with plutonium sent to the repository at every cycle2 .same as item 1 with plutonium sent to the LMFBR as fuel3. PT cycles continued indefinitely.Cross-section and isotope inventory data are taken from the literature for similar facilities and processes and converted to an effective cycle-by-cycle burnup pattern. The effect of PT on potential population hazard into the indefinite future is evaluated on the basis of activity leached from the repository, transported by groundwater, and ingested. The calculation is carried out with two different sets of losses of actinides from facilities, one of which includes very small uranium and plutonium losses. The short-term fatalities expected due to accidents and operational releases are increased up to 67%. The decrease in long-term potential hazard with PT is minimal with the standard loss fractions. In the small loss set, the loss of uranium (which dominates the long-term hazard) is assumed to be very small. The factor of 25 reduction observed in this case is reduced to a factor of 3 when uranium is deleted from the tally. With uranium deleted, both loss fraction sets give the same long-term hazard reduction with PT.