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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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ANS hosts an overview of its STEM resources
The American Nuclear Society recently hosted a webinar charting the programs and resources that the Society can provide to students, educators, and the public regarding nuclear science and technology education—with a particular focus on the K–12 space. The webinar, led by ANS senior manager of STEM programs Uchenna Ezibe, also provided updates on the progress and future of ANS STEM efforts.
Click here to watch the full webinar.
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.