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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
S. S. Christopher, J. J. Koziol, D. E. Mahagin
Nuclear Technology | Volume 6 | Number 1 | January 1969 | Pages 47-55
Technical Papers and Note | doi.org/10.13182/NT69-A28266
Articles are hosted by Taylor and Francis Online.
Two fuel elements containing 0.05 wt% B4 C in 6% enriched UO2, were irradiated in the Saxton reactor to burnups of ∼1000 and 5000 MWd per metric ton of uranium at peak heat ratings of 17.2 and 19.8 kW/ft, respectively. These elements were fabricated by vibratory compaction to densities of 88 ± 2% of theoretical with local boron concentrations maintained within a variation of ∼ ± 20% of the nominal loading. The postirradiation examination revealed no significant dimensional changes in either element and no axial boron redistribution of any consequence. However, the boron migrated radially outward in both irradiated fuel elements. The boron redistribution does not appear to be a function of burnup but depends heavily on the thermal gradient during irradiation. Its effect on core physics was analyzed using the THERMOS program, and the changes in ηf(ratio of neutrons produced to thermal neutrons absorbed) and Δρ (difference in core reactivity) were found to be minimal.