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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.
S. J. Raffety, J. T. Mihalczo
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 433-443
Technical Paper | doi.org/10.13182/NSE72-A22511
Articles are hosted by Taylor and Francis Online.
A series of clean critical experiments has been performed with homogeneous mixtures of finely divided U(2)F4 or U(3)F4 dispersed in dispersed in paraffin with H/235U atomic ratios varying from 133 to 972. The assemblies were constructed in rectangular geometry, and minimum critical masses and volumes in cylindrical and spherical geometries were obtained from buckling conversions. The minimum critical spherical volumes of a U(2)F4-paraffin mixture when unreflected and when reflected with an effectively infinite solid hydrogenous material are 199 and 138 liters, respectively, and the minimum critical 235U masses are 7.5 and 5.4 kg, respectively. The experiments with the U(3)F4-paraffin mixtures were not extensive enough to determine experimentally the values at optimum moderation but transport theory calculations indicate that the unreflected and reflected minimum critical volumes are about 93 and 57 liters, respectively, and that the minimum critical masses are about 4.1 and 2.7 kg of 235U, respectively. Measurements of the 238U-to-235U fission ratio indicated that in some assemblies as much as 6.5% of the fissions occurred in 238U. Prompt-neutron decay constants, α = βeff/1 were measured in reflected and unreflected delayed-critical assemblies of several fuel mixtures by the pulsed-neutron technique; the infinite-medium neutron multiplication factor, k∞, for the various fuel mixtures was inferred from height perturbation measurements.Transport theory calculations of k∞ and feff have been made using various cross-section sets.