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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
M. R. Ioan, G. Bubueanu, C. S. Tuta
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 291-296
Technical Paper | doi.org/10.1080/15361055.2020.1711850
Articles are hosted by Taylor and Francis Online.
This paper reports the results of radiological measurements taken for the last 3 years in the controlled area and adjacent zone of the Tritium Laboratory of the the Horia Hulubei National Institute for Physics and Nuclear Engineering, Magurele. The radiological characterization has been performed by determination of total and removed tritium contamination for the following surfaces: pavement, walls, windows, radiochemical tables, radionuclide fume cupboards, glove boxes, and sinks. The fixed tritium contamination does not present representative radiological risk because beta particles emitted by tritium are unable to penetrate the skin. The removed tritium contamination represents that component of the total surface contamination that can be taken by mechanical processes. The removed contamination was analyzed as a priority because it represents the main radiological risk factor in tritium laboratories. The determination of surface contamination has been carried out by scanning of the analyzed surfaces using an LB 1230 UMo tritium surface monitor with an LB 1230 detector and by a smear test using extruded polystyrene smears followed by measurement of the removed activity with a liquid scintillation counter. The total surface contamination values, obtained by scanning, were below the detection limit of the equipment, except for radiochemical hood surfaces. The removed tritium contamination determined values are in the domain of 5 … 450 Bq/dm2. At the department level, the obtained values for surface tritium contamination are at the background level.