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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Carmen García-Rosales, Sigrid Deschka, Wolfgang Hohenauer, Reiner Duwe, Eric Gauthier, Jochen Linke, Martin Lochter, Werner K. W. M. Malléner, Laurenz Plöchl, Peter Rödhammer, Armando Salito, Asdex-Upgrade Team
Fusion Science and Technology | Volume 32 | Number 2 | September 1997 | Pages 263-276
Technical Paper | First Wall Technology | doi.org/10.13182/FST97-A19896
Articles are hosted by Taylor and Francis Online.
Tiles of fine-grain graphite coated with tungsten layers by different plasma spray techniques (thickness 100 to 550 µm) and by physical vapor deposition (PVD) (thickness 20 to 100 µm) were subjected to heat fluxes, as expected for the divert or of the Axially Symmetric Divertor Experiment (ASDEX)-Upgrade tokamak. By a stepwise increase of the applied heat flux up to 16 MW/m2 and different pulse durations (1 to 5 s), the maximum load for disabling damage of the coating was determined. The fatigue behavior of the coatings was investigated by cyclic loading. The results show that plasma spray coatings are able to withstand heat loads up to 15 MW/m2 for a 2-s pulse without structural changes and cyclic loading with 1000 cycles at 10 MW/m2 and a 2-s pulse. The PVD coatings show damage by crack formation and melting at slightly lower heat loads than most of the plasma spray coatings. Under cyclic loading, the thin PVD coatings fail by extensive crack formation. The results of the tests indicate that the good performance of the plasma spray coatings is related to their higher porosity, which provides a crack-arresting mechanism, and to their mechanical strength.