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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
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 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.
Masatoshi Kondo et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 190-194
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8900
Articles are hosted by Taylor and Francis Online.
Molten salt LiF-BeF2 (Flibe) is one of candidates for self-cooled tritium breeder in fusion blanket system. The Ni based alloys of Hastelloy C-276 (6.28Fe, 15.67Cr, 0.42Mn, 15.83Mo, 3.34W, Ni as balance), Inconel 600(7.02Fe, 15.75Cr, Ni as balance) and Inconel 625 (4.12Fe, 21.94Cr, 9.10Mo, Ni as balance) are candidates of structural material of blanket loop components at down stream. Corrosion characteristics of these alloys were investigated by corrosion test in static Flibe at 500°C and 600°C for 1000 hours. The corrosion rates were estimated from the weight losses of specimens, and those of Hastelloy C-276, Inconel 600 and Inconel 625 in Flibe at 600°C were 3.4m/year, 2.8m/year and 1.1m/year, respectively. The mass balance between the weight losses of specimens and the increase of impurity in Flibe by the exposure was investigated, and it was found that the corrosion was mainly caused by the depletion of Cr from the alloys. The corroded surface had high Ni concentration after the Cr depletion by corrosion, and this is expected to be corrosion resistant in Flibe.
