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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.
M. J. Hazzan, M. S. Stocknoff, David W. Barcomb, Timothy Irving
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 249-256
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33608
Articles are hosted by Taylor and Francis Online.
To perform a realistic dose assessment, a data collection program was initiated to determine what balance of plant systems contribute to operational exposure. Six utilities that operate boiling water reactors participated in the program. As a result of the study, systems or components that were most important with respect to crud-based radiation were identified. The study focused on the following systems: residual heat removal, spent fuel cooling and cleanup, transverse in-core probes, flow and equipment drains, feed, reactor water cleanup, and steam systems. During the study, additional components or systems where no crud-based radiation was expected were identified, e.g., control rod drive pumps, scram discharge volumes, and certain condensate system equipment. It is expected that this information will help utility operators limit crud-producing radiation doses by providing prior knowledge of potential and buildup.