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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.
Jing Pan, Weiwei Xu, Weibin Xi, Mingzhun Lei, Xufeng Liu, Songtao Wu, Kun Lu, Jing Wei, Yuntao Song
Fusion Science and Technology | Volume 77 | Number 6 | August 2021 | Pages 477-488
Technical Paper | doi.org/10.1080/15361055.2021.1936376
Articles are hosted by Taylor and Francis Online.
The evaluation of electromagnetic (EM) loads acting on conductive structures is one of the critical problems for tokamaks. This paper focuses on the main conductive components of the Chinese Fusion Engineering Test Reactor (CFETR), which are vacuum vessel (VV) and blanket components. A multiscenario EM load-calculating simulator is developed. The simulator adopts circuit equations for the calculation of eddy current, magnetic field, and resulting EM loads acting on the VV. And for EM loads acting on the blanket components, an integral parameter method is applied. With the circuit equations and pre-obtained integral parameters implanted in the simulator, EM loads on the CFETR VV and blankets at different scenarios can be evaluated quickly. Results indicate that the simulator can be conveniently used for multiscenario and real-time EM assessment of the tokamak VV and blanket components.
