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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Ryuta Kasada, Hironobu Ono, Hideo Sakesegawa, Takanori Hirose, Akihiko Kimura, Akira Kohyama
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 145-149
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A324
Articles are hosted by Taylor and Francis Online.
To improve material properties of reduced-activation ferritic steels, mechanical properties and microstructure of the steels with adjusting minor alloying elements, such as N, B, Ta, and Ti were investigated. If it became necessary to reduce N contents in the steels for nuclear consideration, B-addition would have the potential to produce a steel comparable, at least in terms of mechanical properties before irradiation, to the JLF-1 IEA heat. Increasing the Ta contents could induce further grain refinement in the JLF-1 steel, but had no significant effect on the tensile and impact properties.