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GAIN makes diverse selections for its third round of awards this year
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear has recently awarded four third-round fiscal year 2026 vouchers to support the development of innovative nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards Idaho National Laboratory, Oak Ridge National Laboratory, and Sandia National Laboratories are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
A.M. McKay, C.H. Cheh
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2206-2212
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24610
Articles are hosted by Taylor and Francis Online.
Catalytic reactors based on the water gas shift reaction were designed, built and tested to provide data for the design of a prototype reactor as an alternative to the uranium hot metal beds in a Fusion Fuel Clean Up (FCU) system. The reactor was designed so it could be implemented into a FCU using only existing technology. A closed loop system was chosen so that safety and net efficiency would not be compromised during upset conditions. The system uses only pure reactants thus eliminating the requirement for a carrier gas. The prototype reactor contains only 10 g of catalyst and is expected to last at least five years. The reactor is small and operates at ∼490 K. It will convert water to hydrogen, at a CO/H2O ratio of 1.5 with greater than 98% efficiency and with an estimated 95% efficiency for a tritiated stream of 90 000 Ci/day. This small decrease in efficiency is not expected to be a concern in the closed loop system proposed. Results show that the reactor performance is very stable even during upset conditions, wide ranges of flow, CO/H2O variance upward from 1.3, and the presence of various contaminants. The maximum tritium inventory during operation in a FCU system is calculated to be 10.4 Ci. The expected waste disposal inventory of the reactor is 3.2 Ci.