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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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Fusion Science and Technology
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Latest News
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
H. Y. Khater, M. E. Sawan
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 581-585
International Thermonuclear Experimental Reactor (ITER) (Poster Session) | doi.org/10.13182/FST98-A11963676
Articles are hosted by Taylor and Francis Online.
A detailed three-dimensional model (3-D) has been developed for the divertor cassette in the ITER design. The layered configurations of the dome PFC and vertical targets were modeled accurately with the front tungsten layer modeled separately. 3-D neutronics calculations have been performed to determine the detailed spatial distribution of the neutron flux in the divertor cassette. A detailed activation analysis has been performed for zones representing the different critical components of the divertor cassette. The calculations have been performed for two operational scenarios. Special attention has been given to the top 1 cm tungsten layer of the divertor dome. The radioactivity generated in the tungsten layers of the divertor is mostly dominated by W during the first day after shutdown. The GlidCop copper and 316 SS-LN parts of the divertor also generated considerable levels of activity and decay heat. Nevertheless, the analysis showed that the tungsten Plasma Facing Component (PFC) is clearly the most critical part of the divertor from the decay heat generation point of view.