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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.
Jeffery F. Latkowski, Javier Sanz, Jasmina L. Vujic, Michael T. Tobin
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1475-1479
Safety and Environment | doi.org/10.13182/FST96-A11963157
Articles are hosted by Taylor and Francis Online.
The majority of radionuclide generation/depletion codes consider only neutron reactions and assume that charged particles, which may be generated in these reactions, deposit their energy locally without undergoing further nuclear interactions. Neglect of sequential charged-particle (x,n) reactions can lead to a large underestimation in the inventories of radionuclides that make a significant impact upon various radiological indices.1 We have adopted the PCROSS code for use with the ACAB activation code to enable calculation of the effects of (x,n) reactions upon radionuclide inventories and inventory-related indices.2,3 The present work builds upon our previous work and the work completed by R. A. Forrest for magnetic fusion energy devices.4,5 Using this capability we have performed activation calculations for Flibe (2LiF + BeF2) coolant in the HYLIFE-II inertial fusion energy (IFE) power plant design. For pure Flibe coolant, we find that (x,n) reactions dominate the residual contact dose rate at times of interest for maintenance and decommissioning. For impure Flibe, however, radionuclides produced directly in neutron reactions dominate the contact dose rate, and (x,n) reactions do not make a significant contribution. Our results demonstrate the potential importance of (x,n) reactions and that the relative importance of (x,n) reactions varies strongly with the composition of the material considered. Future activation studies should include (x,n) reactions in all calculations until a method for screening their importance in a particular situation has been established.
