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Fusion Science and Technology
Latest News
Argonne research aims to improve nuclear fuel recycling and metal recovery
Servis
Scientists at Argonne National Laboratory are investigating a used nuclear fuel recycling technology that could lead to a scaled-down and more efficient approach to metal recovery, according to a recent news article from the lab. The research, led by Argonne radiochemist Anna Servis with funding from the Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E), could have an impact beyond the nuclear fuel cycle and improve other high-value metal processing, such as rare earth recovery, according to Argonne.
The research: Servis’s work is being carried out under ARPA-E’s CURIE (Converting UNF Radioisotopes Into Energy) program. The specific project—Radioisotope Capture Intensification Using Rotating Packed Bed Contactors—started in 2023 and is scheduled to end in January 2026.
Dongxun Zhang, Wei Liu, Wenguan Liu
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 543-552
Technical Paper | doi.org/10.1080/15361055.2020.1725368
Articles are hosted by Taylor and Francis Online.
With the method of gas-driven permeation, a series of permeation experiments was carried out using Hastelloy N alloy membrane in an elevated temperature range of 400°C to 800°C with different hydrogen isotopes. A complete set of permeability, diffusivity, and Sieverts’ constant for hydrogen and deuterium in Hastelloy N alloy was successfully obtained. The isotope effect in the diffusion process was analyzed and compared with references. The ratios of diffusive transport parameters for hydrogen and deuterium were a permeability ratio of ФH/ФD = 1.32exp(0.34kJ/RT), a diffusivity ratio of DH/DD = 1.15exp(−0.41kJ/RT), and a Sieverts’ constant ratio of KS,H/KS,D = 1.16exp(0.21kJ/RT). The result that the permeation flux of deuterium was decreased after introducing hydrogen could be used to suppress the permeation of tritium in future tritium control of the Fluoride-salt-cooled High-temperature Reactor (FHR). Compared with NiO, the Cr2O3 formed in the surface oxidation layer of Hastelloy N alloy showed better hydrogen permeation barrier performance after baking above 700°C in air.
