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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Alice Y. Ying, Mark S. Tillack
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 990-995
Blanket Technology | doi.org/10.13182/FST91-A29471
Articles are hosted by Taylor and Francis Online.
Laminar heat transfer in self-cooled liquid metal blankets can be enhanced by increasing the aspect ratio of the ducts. To determine the potential benefits of elongated rectangular ducts, numerical simulations of MHD fully-developed flow and developing heat transfer were performed. Results show that as the aspect ratio increases (i.e., the ratio of the side wall to Hartmann wall length), the peak velocity and side layer flow quantity increase, which leads to enhancement of the average heat transfer coefficient along the side layer. The pressure gradient decreases with increasing elongation, providing an added benefit. However, results of the heat transfer analysis also indicate that the non-uniformity along the heated wall and the peak wall temperature both increase as the aspect ratio increases, due to smaller velocities in the corners and near the interface between the side layer and the core. The net benefit to reactor blanket design is therefore uncertain, because designs are usually constrained by the peak structure temperature. At fixed velocity, elongated ducts always have higher peak temperatures. However, the reduction in pressure gradient allows the designer to increase the average velocity, which improves thermal performance due to lower bulk temperature rise as well as higher wall heat transfer coefficient. Calculations show that peak temperatures can be reduced relative to the square duct case with lower pressure gradient by optimizing the velocity. Elongated ducts may suffer from larger pressure stresses due to geometric factors. Thermal stresses are also likely to increase, owing to the increased thermal gradients in the walls. Overall, it is difficult to guarantee that elongation will provide improved performance without a more detailed design analysis.