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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.
A. F. Moscati, R. C. Erdmann
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 184-190
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31401
Articles are hosted by Taylor and Francis Online.
Ionizing radiation will have both somatic and genetic effects upon the exposed populations. Somatic changes, i.e., effects produced directly in the irradiated organism, will result in the death of the irradiated species by a variety of natural mechanisms. Genetic effects, however, are more subtle and may sometimes be viewed as beneficial; however, the benefits accruing to subsequent generations have yet to be demonstrated for marine species. Two models for predicting the impact of radioactivity in the food chain upon man are reviewed here: (a) the critical pathway concept, and (b) the specific activity approach. The specific activity method was used by Aten in 1961 to obtain estimates of the maximum permissible concentrations of biologically important radionuclides in seawater (MPC)s. In an accident situation involving the release of radioactivity from a light-water power reactor to the ocean, the most important radionuclides on the basis of the type of radiations emitted, quantity produced, half-life, and biological significance are the fission products 90Sr, 137Cs, 239Pu, and the activation products 65Zn, 54Fe, and 95Zr. The specific activity approach as applied to three classes of accidental radioactive releases to the sea can be used to determine the sensitive nuclide for each release and to estimate the relative degree of seriousness of each release by calculating the volume of seawater needed to dilute each spill to the (MPC)S of the critical nuclide. Estimates made for three types of accidental releases at sea yield the following data: