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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.
Victor E. Grob, E. Santandrea, Hilmar Ritz
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 514-524
Technical Paper | doi.org/10.13182/NSE60-A25760
Articles are hosted by Taylor and Francis Online.
As part of the Yankee and the Belgian Reactor-3 Critical Experiments program at the Westinghouse Reactor Evaluation Center, measurements have been made of the parameters leading to p, f, and ϵ in a light-water moderated heterogeneous reactor with slightly enriched UO2 fuel rods clad in stainless steel. A detailed description of this reactor is given in reference 1. Measurements were made using 4.48% and 2.73% enriched fuel with lattice pitches of 0.470 and 0.435 in. The individual UO2 sintered pellets, in the fuel rods, had a diameter of 0.300 in. and a length of 0.600 in. The 4.48% and 2.73% fuel rods contained 90 and 80 pellets, respectively. The stainless steel cladding was 0.305 in. i.d. and 0.347 in. o.d. for the 4.48% enriched fuel, and 0.306 in. i.d. and 0.338 in. o.d. in the case of 2.73% enrichment. The measurements were performed using a higher fuel enrichment than used previously at Bettis (2, 3) and elsewhere for similar experiments, thus uncovering a large unexplored range of enrichments.