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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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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.
S.-H. Hong, K.-M. Kim, J.-H. Song, E.-N. Bang, H.-T. Kim, K.-S. Lee, A. Litnovsky, M. Hellwig, D. C. Seo, H. H. Lee, C. S. Kang, H.-Y. Lee, J.-H. Hong, J. G. Bak, H.-S. Kim, J.-W. Juhn, S.-H. Son, H.-K. Kim, D. Douai, C. Grisolia, J. Wu, G.-N. Luo, W.-H. Choe, M. Komm, M. van den Berg, G. De Temmerman, R. Pitts
Fusion Science and Technology | Volume 68 | Number 1 | July 2015 | Pages 36-43
Technical Paper | Open Magnetic Systems 2014 | doi.org/10.13182/FST14-897
Articles are hosted by Taylor and Francis Online.
One of the main missions of KSTAR is to develop long-pulse operation capability relevant to the production of fusion energy. After a full metal wall configuration was decided for ITER, a major upgrade for KSTAR was planned, to a tungsten first wall similar to the JET ITER-like wall (coatings and bulk tungsten plasma-facing components). To accomplish the upgrade, tungsten bonding technology has been developed and tested. Since the leading edges of each castellation structure have to be protected, shaping of tungsten blocks has been studied by ANSYS simulation, and the miniaturized castellation has been exposed to Ohmic plasma to confirm the simulation results. It is found that a shaped castellation block has more heat handling capability than a conventional block. For more dedicated experiments, a multipurpose castellation block is fabricated and exposed to Ohmic, L- and H-mode plasmas and observed by IR camera from the top. During the fabrication and assembly of the blocks, leading edges caused by “naturally misaligned” blocks due to engineering limits with a maximum level up to 0.5 mm have been observed, and these have to be minimized for the future fusion machine.