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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.
Tay-Jian Liu, Yea-Kuang Chan, Yuh-Ming Ferng, Chien-Yeh Chang
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 187-200
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3056
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic phenomena of inadequate core cooling caused by a cold-leg small-break loss-of-coolant accident (SBLOCA) were investigated experimentally at the Institute of Nuclear Energy Research Integral System Test facility. The experiments were performed under the conditions of different break sizes (0.5 and 2%) in the cold leg followed by failure of the high-pressure injection system. The primary system cooldown is implemented by the secondary-side depressurization. The effectiveness of early initiation of the recovery action on reactor safety and related thermal-hydraulic phenomena are examined. The initiation criterion for recovery action considered here is determined by core water levels instead of core exit temperature based on the current emergency operating procedures. The impact of emergency core-cooling flow bypass phenomenon may significantly deteriorate the effectiveness of the recovery operation for a cold-leg SBLOCA. The results showed that the early initiation of secondary-side depressurization can effectively minimize the risk of core damage by preventing fuel rods from heating up throughout the transient. In addition, the core suffers a rather moderate thermal stress during the cooldown process.