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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.
L. H. Rovner, G. R. Hopkins
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 274-302
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31593
Articles are hosted by Taylor and Francis Online.
The (low-atomic-number ceramic) materials carbon, SiC, Be2C, B4C, TiC, BN, Si3N4, Al2O3, and BeO provide a range of property values that are useful for evaluating range of applicability of low-atomic-number ceramic materials in fusion reactors. A survey of recent literature provides a base for conceptual design analyses of two first wall concepts: (a) a radiation-cooled simple plate liner and (b) a pressurized helium, forced convection-cooled tubular assembly. The first case is limited in heat load by maximum material temperature, and the second by either temperature or stress. Maximum temperatures are limited by vapor pressure or chemical reaction rates with plasma hydrogen, both resulting in release of impurities to the plasma. Silicon carbide and carbon appear most suitable for first wall materials, with estimated wall loading limits in the range from 1 to >5 MW/m2 of incident 14-MeV neutrons.