ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
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.