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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
R. E. Kothmann, L. Green, M. D. Carelli, M. J. Manjoine, R. E. Wootton
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 551-557
Fusion Material and Plasma-Facing Component | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40215
Articles are hosted by Taylor and Francis Online.
Use of vanadium alloys is contemplated for the ITER blanket and guidance is needed to determine the extent of the data base for qualifying these alloys as structural material. A probabilistic methodology first employed in the fast breeder program is used to provide a preliminary assessment of the data base requirements. This methodology, which is applicable to any structural material, or in general to any design variable, determines the adequacy of the design by considering simultaneously all design affecting uncertainties, such as operational, nuclear, thermal-hydraulic, structural, geometric tolerances and material properties. In this study a thermal-mechanical calculational model of the ITER self cooled lithium blanket design was developed and the effect of design uncertainties on temperature (creep limited) and stress-strain (fatigue limited) were calculated. Based upon the current design, it was concluded that an uncertainty band of ± 30% on vanadium material properties is acceptable. Confirmatory irradiation data are however necessary.