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Division Spotlight
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.
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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Nuclear Technology
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May 2025
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.
L. El-Guebaly, R. Kurtz, M. Rieth, H. Kurishita, A. Robinson, ARIES Team
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 185-189
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12349
Articles are hosted by Taylor and Francis Online.
The development of radiation-resistant materials to sustain the harsh fusion environment represents a challenging task for divertor designers. In recent years, advanced physics simulations of the power leaving the plasma with radiation and charged particles indicate much higher heat fluxes to the divertor than previous estimates. In response, experts in EU, Japan, and US developed several W alloys for advanced He-cooled divertors that can handle heat fluxes in excess of 10 MW/m2. This paper briefly discusses the ongoing effort to develop W alloys suitable for fusion applications, the challenging phenomena impacting the behavior of W under a fusion environment, and the environmental impact of the most promising, state-of-the-art alloys: W-La2O3 and W-1.1TiC.