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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.
Ralph W. Moir
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 1169-1177
Fusion Power Reactor, Economic, and Alternate Concept | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40312
Articles are hosted by Taylor and Francis Online.
If the present research program is successful, heavy-ion beams can be used to ignite targets and to produce high gain for yields of about 350 MJ. HYLIFE-II is a power plant design based on surrounding such targets with thick liquid (Flibe, Li2BeF4) so that the chamber and other apparatus can not only stand up to these 350 MJ bursts of energy but do so without replacing components during the plant's 30-year life. The capacity factor will be increased and the cost of component replacement will be decreased. Continuous improvements to the design are being made to increase safety, decrease the generation of radioactive material, and reduce the cost of electricity (COE). Improvements discussed in this paper decreased COE for each effect by the amount in parentheses: increased plant size (22%), increased capacity factor and reduced component replacement (20%), reduced remote maintenance equipment (3.2%), use of non-nuclear grade chamber, pumps and piping (2.9%), reduced tritium inventory by a factor of 2.4, reduced excess tritium production with attendant increase energy release in the blanket (1.8%), corrected treatment of Flibe inventory costs (3.4%).