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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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. Harb, D. Leichtle, B.-Y. Kim, J.-P. Martins, J. G. van der Laan, J. Bergman, E. Polunovskiy, A. Serikov
Fusion Science and Technology | Volume 79 | Number 3 | April 2023 | Pages 305-319
Technical Paper | doi.org/10.1080/15361055.2022.2109368
Articles are hosted by Taylor and Francis Online.
One of the advances in the test blanket module program within the ITER project in the last few years concerned the evolution of the pipe forest (PF) and bioshield plug (BP) designs. In support of the design phase, nuclear analyses to assess several responses in the fusion neutronics environment inside the port interspace (PI) with the existence of the evolved PF and BP are deemed essential. Nuclear analyses were commenced using the new PF and BP with developing the neutronics models and performing preliminary assessment of the radiation fields and shutdown dose rate (SDDR) in the PI. In this paper, the results of a full suite of nuclear analyses are discussed, which covers more configurations and radiation sources, in two plasma operational modes: on and off. For the plasma-on mode, different shielding options were examined. The results show a clear benefit of combining the installation of shielding panels on the PF enclosure with those in the BP “dogleg,” through which the pipes penetrate to the port cell area. For the plasma-off mode, the SDDR was assessed from different sources: activated components and residual LiPb layers in pipes after drainage. As maintenance operations are foreseen during the lifetime of the facility, the SDDR was also assessed for access conditions, open BP doors, and transport conditions, with PF extracted in the gallery.