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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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Latest News
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.
G. W. Hollenberg, R. H. Jones, G. E. Lucas
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1701-1706
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29587
Articles are hosted by Taylor and Francis Online.
Ceramic/ceramic composites, in particular, SiC/SiC composites, offer two major advantages over conventional structural metals for fusion applications; i.e., low activation under neutron irradiation and high temperature mechanical properties. These composites face several challenging issues which include: fabrication scale up, joining methods, and chemical compatibility. Inherent porosity, together with microcracking that occurs during stressing beyond the yield strength may negate the consideration of these composites for hermetic boundaries unless combined with other materials. Irradiation stability is an issue until better data can be obtained. Hence, the feasibility of using these composites in a fusion structure remains to be established.