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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.
J. Rapp, A. Lumsdaine, C. J. Beers, T. M. Biewer, T. S. Bigelow, J. F. Caneses, J. B. O. Caughman, R. H. Goulding, N. Kafle, C. H. Lau, E. Lindquist, P. A. Piotrowicz, H. Ray, M. Showers, the MPEX Team
Fusion Science and Technology | Volume 75 | Number 7 | October 2019 | Pages 654-663
Technical Paper | doi.org/10.1080/15361055.2019.1610315
Articles are hosted by Taylor and Francis Online.
The Prototype Material Plasma Exposure eXperiment (Proto-MPEX) is being used to qualify the plasma source and heating systems for the Material Plasma Exposure eXperiment (MPEX). The MPEX will address important and urgent research needs on plasma material interactions for future fusion reactors. In MPEX, plasma-facing components (nonirradiated and a priori neutron irradiated) will be exposed to plasma conditions as they are expected in future fusion reactors. The MPEX, a steady-state device enabled by superconducting magnets, will be able to break into new ground by assessing plasma-facing materials and components at an ion fluence level in the range of 1030 to 1031 m−2. To achieve the relevant plasma conditions, high-density plasmas (>4 × 1019 m−3) are produced with a high-power helicon source. The so-produced low-temperature helicon plasma is then additionally heated with waves in the ion cyclotron resonance frequency and electron cyclotron resonance frequency domains. Proto-MPEX has achieved all key parameters (source ne, source Te, source Ti, target Te, target Ti, target ion flux, and target heat flux) within a factor of 2 of the design requirements of MPEX, albeit not simultaneously. These parameters were achieved with a total installed heating power of 330 kW, which is less than half of the planned heating power in the MPEX (800 kW). An overview of the latest results from Proto-MPEX is given. These results are shown in relationship to the MPEX system goals. Remaining necessary research and development tasks are discussed. The MPEX is currently in the conceptual design phase. The status of the design and an overview of the system requirements are presented.