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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.
M.Z. Youssef, Y. Watanabe, M. Abdou, M. Nakagawa, T. Mori, K. Kosako, T. Nakamura
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1299-1308
Blanket Nucleonics Experiment | doi.org/10.13182/FST89-A39869
Articles are hosted by Taylor and Francis Online.
Several fusion-oriented integral experiments were performed in Phase II of the U.S./JAERI Collaborative Program on Fusion Neutronics where the geometrical configurations and source condition closely simulate the incident spectrum in fusion reactors. The main objective of the program is to estimate the uncertainties involved in predicting tritium breeding rate in Li2O and other neutronics parameters in fusion blankets that include engineering features (i.e., first wall, multiplier). In Phase II, the Li2O test assembly is placed on one end of a Li2CO3 enclosure that houses the D-T neutron source. Predicted local and integrated tritium production rates (TPR) from 6Li(T6), 7Li(T7) and natural lithium (TN) were compared to measurements in various configurations that included reference, first wall and beryllium multiplier experiments (Phase IIA) in addition to repeating these experiments with a FW/Be layer covering the interior surface of the Li2CO3 enclosure (Phase IIB). Other neutronics parameters that included source characterization by foil measurements, in-system reaction rates, and in-system spectrum measurements were also analyzed. The analyses were carried out independently by both parties using various 3-D Monte Carlo codes and 2-D discrete ordinates codes and data libraries. The results of the analyses are reported in this paper with emphasis placed on the impact of the beryllium data on the discrepancies found between predictions and measurements.