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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.
B. F. Picologlou, Y. S. Cha, S. Majumdar
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 848-853
Liquid-Metal Blankets and Magnetohydrodynamic Effects | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24843
Articles are hosted by Taylor and Francis Online.
The reactors considered in the Tokamak Power Systems Studies (TPSS), with their reduced toroidal magnetic flux densities, increased aspect ratios, and moderate overall power outputs afford the possibility of significant improvements and simplification in the design of liquid-metal self-cooled blankets. In designing the first wall and blanket structural, thermal, and magnetohydrodynamic constraints must be satisfied simultaneously. A systematic approach to do so efficiently, and resulting design parameters are presented. Designs with separate limiters can achieve a neutron wall loading capability of about 5 MW/m2 with bare structural walls near the first wall and insulated laminated construction in regions of low fluence only. When laminated wall construction is used in the first wall coolant channels, the neutron wall loading capability exceeds 10 MW/m2.