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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.
Joe E. Dahlquist, Fred S. GL, Ralph A. Nelson
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 252-262
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33558
Articles are hosted by Taylor and Francis Online.
During normal and accidental operations of a light water nuclear reactor, a wide range of thermal-hydraulic conditions may be encountered for which the critical heat flux (CHF) cannot be predicted by a single correlation. An encompassing model was developed for predicting the steady-state forced convective CHF for water over a wide range of thermal-hydraulic conditions. A CHF model is postulated using a conceptual CHF map to define possible CHF mechanisms for given thermal-hydraulic conditions. Existing steadystate CHF correlations, for which the primary CHF mechanism modeled can be identified, are then used in conjunction with the conceptual CHF map to construct a predictive CHF model. The CHF correlations used as the foundation of this model are the Westinghouse-3, the Biasi, and the Modified-Barnett correlations. These correlations allow coverage of a wide range of thermal-hydraulic conditions, provide favorable comparison with experimental data, and are commonly used in the nuclear industry. The parametric ranges covered by the resultant model are
0.3 < P (MPa) <16.0
6.0 <D (mm) <30.0
100.0 <G (kg/m2·s) < 8000.0
−0.3 <X (dimensionless) < 1.0,where P is pressure; D, the hydraulic diameter; G, the mass flux; and X is quality. The CHF model compares favorably with available experimental data and was used to construct specific CHF maps.
