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NRC grants license for TRISO-X fuel manufacturing using HALEU
The Nuclear Regulatory Commission has granted X-energy subsidiary TRISO-X a special nuclear material license for high-assay low-enriched uranium fuel fabrication. The license applies to TRISO-X’s first two planned commercial facilities, known as TX-1 and TX-2, for an initial 40-year period. The facilities are set to be the first new nuclear fuel fabrication plants licensed by the NRC in more than 50 years.
B. W. N. Fitzpatrick, J. W. Davis, A. A. Haasz
Fusion Science and Technology | Volume 73 | Number 4 | May 2018 | Pages 552-558
Technical Note | doi.org/10.1080/15361055.2017.1404346
Articles are hosted by Taylor and Francis Online.
If both carbon and tungsten were to be part of the plasma-facing armor in a future fusion reactor, it is inevitable that carbon co-deposits containing tungsten impurities will form. This work examines the effectiveness of thermo-oxidation in removing hydrogen from W-containing carbon co-deposits. Amorphous deuterated hydrocarbon (a-C:D) films were created with a CD4/Ar direct-current glow discharge and doped with W sputtered from a W mesh in front of the specimen. The W concentration in the specimens ranged from 0 to 35 at. % W/(W + C). The films were oxidized at 350°C, in 2 Torr pure O2 for time increments totaling 8 h. The D content of the films was measured before and at various stages of the oxidation exposure using laser thermal desorption spectroscopy. Essentially all deuterium was removed from films containing very little or no W doping [<0.1% W/(W + C)]. For films with more W [few percent W/(W + C)], oxidation was less effective at removing D. For two specimens with 2.4% and 35% W/(W + C), oxidation was completely ineffective at removing D.