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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
W. Baer
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 57-60
Technical Paper | doi.org/10.13182/NSE61-A25930
Articles are hosted by Taylor and Francis Online.
A measurement of the epithermal radiative capture in U238 has been carried out in a natural UO2-fueled blanket cluster of the nuclear mock-up of PWR Core 1. Analysis indicates that a substantial increase (∼20%) in epithermal captures in a natural uranium metal plate fuel cluster should occur in the fuel elements adjacent to a wide intercluster water channel. The experiment shows that the captures in a cylindrical UO2 fuel element at the edge of the bundle is only 7% greater than in a neighboring fuel element. However, the radial distribution of captures in the first fuel rod shows that the captures near the wide intercluster water channel are 65% greater than at an equivalent position on the side of the rod away from the water channel. Calculations of the relative epithermal U238 captures in the cluster have shown that diffusion theory predicts the spatial dependence of the captures in the interior of the cluster but fails near the edge of the bundle. Monte Carlo analysis confirms the observed increase in the captures in a fuel rod at the edge of the bundle, although the precision of the analysis does not make a quantitative comparison feasible.