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Conference Spotlight
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.
Yong-Seok Choi, Dong-Hoon Kam, Byong-Guk Jeon, Jong-Kuk Park, Sang-Ki Moon
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2711-2722
Research Article | doi.org/10.1080/00295639.2022.2132100
Articles are hosted by Taylor and Francis Online.
Insufficient thermal-hydraulic knowledge for analysis of a reactivity-initiated accident demands experiments of fast-transient flow boiling heat transfer from moderate- to high-pressure conditions. In this study, those experiments are conducted for vertical upward tube flows of pressurized water. The tube wall is joule heated by stepwise electric pulse power to achieve an abrupt wall heating condition. The applied pulse power is varied from 4.68 to 13.59 GW/m3, which is beyond the power required for steady-state critical heat flux (CHF) to occur. Rapid evolution of the boiling wall temperature is extracted from outer wall temperature data by solving an inverse heat conduction problem. As a result, with increasing the applied pulse power, the time to occurrence of departure from nucleate boiling gets shorter, and the corresponding peak heat flux increases over the steady-state CHF, which is evaluated at the same flow condition. A logarithmic relation between the wall heating rate and the CHF increment ratio is also demonstrated. The effects of pressure, inlet subcooling, and mass flux on the transient peak heat flux are also investigated. As the pressure increases, the nucleate boiling duration gets shorter with decreasing peak heat flux. On the other hand, as the inlet subcooling increases, the nucleate boiling duration gets longer, and the peak heat flux increases. Contrarily, the mass flux does not show any noticeable effects on the transient heat transfer evolution.