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Atlanta, GA|Atlanta Marriott Marquis
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Fusion Science and Technology
July 2025
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.
M. Tanaka et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 51-54
Technical Paper | Tritium Science and Technology - Tritium Processing, Transportation, and Storage | doi.org/10.13182/FST05-A878
Articles are hosted by Taylor and Francis Online.
For the purpose of the recovery of a hydrogen isotope exhausted from a fusion device and its application to a tritium monitor, hydrogen extraction properties using SrZr0.9Yb0.1O3- and CaZr0.9In0.1O3- and the effect of the electrode attachment method on the hydrogen extraction were evaluated under various atmospheres and temperatures. As a result, hydrogen could be extracted from mixed gases containing hydrogen, water vapor and methane. Furthermore, water vapor electrolysis for the tritium monitor was also evaluated under a wet atmosphere containing oxygen. From these results, it was revealed that a plated platinum electrode was suitable for mixed gases containing hydrogen, water vapor and methane, and that a porous pasted platinum electrode was suitable for water vapor electrolysis. From the findings obtained from the study of the hydrogen extraction properties, we described an optimum specification of the platinum electrode for a tritium recovery system and the number of proton-conducting ceramics for a tritium monitor.
