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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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.
Werner Heit, Hans Huschka, Wilhelm Rind, Günter G. Kaiser
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 44-54
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33594
Articles are hosted by Taylor and Francis Online.
To cover a large number of possible high-temperature reactor applications in the Federal Republic of Germany, the fuel element is designed to be uniform and acceptable for conditions set by different approaches for various plants following the thorium high-temperature reactor (THTR). To minimize fission product release, silicon carbide coated fuel (Triso) is required for all types of fuel cycles, and limits are specified for both fabrication and in-service coating defects. Fabrication processes using precise classification of coated and overcoated particles by tabling techniques ensure satisfaction of specified limits on fabrication-induced coating defects. A comprehensive irradiation test program was performed for both high-enriched uranium/thorium fuel elements used in the THTR and Arbeitsgemeinschaft Versuchs-Reaktor cycle and the low-enriched uranium fuel elements to be used for follow-up projects. The results demonstrate good performance of all types of fuel.
