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Fuel Cycle & Waste Management
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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Latest News
Argonne creates new methodology for digital twins
Hu
Argonne National Laboratory has added a new twist to digital twin technology for research into nuclear energy. According to Rui Hu, a principal nuclear engineer at Argonne, “Our digital twin technology introduces a significant step toward understanding and managing advanced nuclear reactors, enabling us to predict and respond to changes with the required speed and accuracy.”
The research of Hu and his colleagues, “Development of Whole System Digital Twins for Advanced Reactors: Leveraging Graph Neural Networks and SAM Simulations,” was published in the American Nuclear Society journal Nuclear Technology.
Virtual representation: A digital twin technology is an accurate virtual representation of a complex system. It is updated with real-time data from sensors applied to the physical system, such as a nuclear reactor.
P. K. Kuroda, M. P. Menon
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 70-74
Technical Paper | doi.org/10.13182/NSE61-A25932
Articles are hosted by Taylor and Francis Online.
The occurrence of a number of fission products in pitchblende and in nonirradiated natural and depleted U salts with 10-4 dis/sec/g-U, was recently reported by Kuroda and co-workers. The following nuclides were detected: Sr89, 90, 91, 92, Mo99, I131, 132, 133, 134, 135, and Ba140. These fission products are formed predominantly by the spontaneous fission of U238, and it is possible to obtain the general shape of the mass-yield curve for the spontaneous fission of U238 from the equilibrium activities of the fission products found in nonirradiated U salts. The spontaneous fission half-life of U238 can also be calculated from these data. Radiochemical procedures have been developed for the determination of each fission product, in which a quantity ranging from 0.1 to 1 disintegration/sec of the fission product activity is isolated from kilogram quantities of U salts, purified, and then counted. Where the half-life of the fission product was several months, U minerals instead of U salts, were used. Removal of the bulk of the U by a liquid extraction method was found to be necessary and/or advantageous in most cases, although it was possible to precipitate certain fission products directly from a concentrated solution of the U salts. A new procedure is currently under investigation for the isolation and quantitative determination of the isotopes of Ce by a liquid-liquid extraction method. Ce(IV) can be extracted from a 10 M HNO3 solution by a 1 to 4 mixture of TBP and CCl4 with high extraction efficiency, and further purified by a combination of oxidation-reduction and liquid-liquid extraction procedures.