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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.
E. T. Laats, T. R. Schmidt, J. A. Reuscher
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 68-76
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31539
Articles are hosted by Taylor and Francis Online.
Experiments have been performed recently at Sandia Laboratories to investigate and characterize potential fuel materials for fast burst reactors. A novel technique has been developed to determine the thermomechanical properties of fuel materials under actual use conditions. The Sandia Pulsed Reactor II is used to rapidly fission heat a thin rod of the sample material, supported at its center, thereby inducing longitudinal stress waves in the sample. The dilation history at the ends of the rod and the temperature of the rod are recorded. A measure of the internal friction is determined from the decay of the longitudinal oscillations induced in the sample. The materials examined include uranium, U—0.78 wt% Ti, U— 6 wt% Mo, and U—10 wt% Mo. The first two are alpha-phase materials in a wrought condition, while the second two are gamma-phase-stabilized materials in an “as cast” condition. The alpha-phase wrought materials had higher internal friction than the gamma-phase “as cast” materials, with uranium being the highest by approximately two orders of magnitude as compared to U— 10 wt% Mo, the lowest.