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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.
Hyun Seok Kim, Hyunsun Han, Ki Min Kim, Jwa-Soon Kim, Sang Hee Hong
Fusion Science and Technology | Volume 55 | Number 2 | February 2009 | Pages 95-99
Technical Paper | Seventh International Conference on Open Magnetic Systems for Plasma Confinement | doi.org/10.13182/FST09-A6990
Articles are hosted by Taylor and Francis Online.
A two-dimensional numerical modeling is carried out to simulate argon plasma-neutral transport in a linear divertor simulator with an axisymmetric cylindrical geometry. A pure argon plasma flow is introduced from the source region into the transport region, and pumped out near the target plate. This numerical modeling is based on a time-dependent Braginskii's fluid formulation for plasma transport and a simple diffusion model for neutral transport. The Bohm diffusion model is adopted for calculation of radial diffusion coefficients across the parallel magnetic field in the simulator. Using the design and operation parameters of the Multi-Purpose Plasma (MP2) facility at the National Fusion Research Institute (NFRI) in Korea, argon plasma properties such as density and temperature distributions are calculated, and the formation of ionization front is found in the transport region. Plasma equilibrium profiles along the near axis turn out to be actually unaffected by the pumping positions along the cylindrical wall. Moreover, a gas target divertor concept is numerically simulated to find out puffing effects as well as pumping roles. As increasing the puffing rate at the target plate, not only the ionization front in the plasma density profile is gradually moving toward the entrance region, but also plasma density and electron temperature at the target are dramatically reduced. Two relatively peaked poles in the neutral density profile are resulted from puffing and recycling neutrals, respectively.