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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.
T.F. Yang, G.S. Luan,† L. Bromberg, D.R. Cohn, B.J. Braams
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 857-863
Advanced Reactor | doi.org/10.13182/FST91-A29452
Articles are hosted by Taylor and Francis Online.
A novel gaseous divertor concept is proposed consisting of gas chamber and pumping at high pressure or by reionizing the neutrals. The concept results in substantial reductions of the plasma temperature and heat flux at the target and the pumping requirement. Fluid model simulations of the scrape-off region of the Aries Reactor design by feeding the gas at the target at a flux of 1 × 1023m−2/s at 0.5 eV has shown that the electron and ion temperatures can be cooled to 20 eV. The heat flux to the target can be reduced from 80 MW/m2 to 6 MW/m2. The plasma temperature and heat flux at the divertor target are monotonically decreasing functions of the neutral incident flux. Interestingly the temperature and the heat flux also decrease with decreasing neutral gas initial flowing speed removing the need of gas jets. The backflow problem can be minimized by including a baffle plate to form a gaseous chamber. Monte-Carlo simulations using test particles have showed that the throat of the gaseous chamber can be practically plugged by the incident plasma to prevent backflow of neutrals into plasma core. The pumping can be facilitated by either operating the divertor chamber at high pressure on the order of 30 torr or reionizing the neutrals traveling to a weak toroidal field region.