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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
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.
Harry J. Reilly, Lawrence E. Peters, Jr.
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 89-95
Technical Paper | Shielding | doi.org/10.13182/NT71-A30905
Articles are hosted by Taylor and Francis Online.
A calorimeter was made to determine the relative amount of gamma heating in watts per gram in different materials as a function of thickness and atomic number. The experiment was performed in the NASA Plum Brook Mockup Reactor, which has a typical light-water test reactor gamma-source spectrum. Carbon, aluminum, zirconium, tin, and lead specimens in slab geometry were irradiated. The results showed no significant difference in the gamma heating in carbon and aluminum, but the heating in the other materials was greater than that in aluminum and carbon. The smaller thicknesses had the greater heating. The calorimeter was also used to determine the gamma-heating effect in an irradiation experiment mockup having cylindrical geometry. The result showed good agreement with an expected value obtained from the slab geometry data. A theoretical analysis of the relative gamma heating was made using a one-dimensional multigroup transport program. It was concluded that the analysis and measurements agreed qualitatively and that quantitative differences were attributable mostly to geometrical effects. The results of this study are believed to be applicable to both nuclear reactor experiment designs and other reactor problems.