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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.
Sergey Pestchanyi, Francesco Maviglia
Fusion Science and Technology | Volume 75 | Number 7 | October 2019 | Pages 647-653
Technical Paper | doi.org/10.1080/15361055.2019.1643684
Articles are hosted by Taylor and Francis Online.
Simulation of divertor target damage during thermal quench of the disruption in the future DEMO tokamak has been performed using the TOKES code. This parametric study includes damage estimation for disruptions of the plasma energy E0 in the DEMO core in the range of 0.4 to 1.3 GJ and of time duration 1 to 2 ms. According to the simulations, the maximum melt depth on the divertor targets is ~80 μm, independent of the energy content in the core. The melted pool maximum area grows from ~20 m2 for 0.4-GJ disruption to ~120 m2 for 1.3-GJ disruption. Maximum erosion depth is 4 μm for 1.3-GJ disruption and decreases to less than 1 μm with decreasing E0. The total quantity of vaporized tungsten ranges from 2 ∙ 1021 to 3 ∙ 1024 atoms for disruptions of 0.4 to 1.3 GJ. An additional parametric study has revealed weak dependence of the results from the characteristic widths λq of the disruptive flux in the scrape-off layer.
