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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.
G. G. Bentle
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 487-495
Technical Paper | doi.org/10.13182/NSE60-A25755
Articles are hosted by Taylor and Francis Online.
A transparent plastic in which gas was formed by gamma irradiation, was used to investigate the mechanisms of gas bubble formation and growth. Bubble formation and swelling were studied for several environments, both external and internal to the plastic-gas systems. During irradiation at 100°C, larger, but fewer bubbles form in the plastic than on lower temperature irradiation followed by 100°C annealing. The data indicate that inclusions increase bubble formation and internal surfaces promote bubble growth. An interpretation of these results, when applied to nuclear fuel swelling, indicates that swelling may be decreased by increasing fission rate and by decreasing the available sites for bubble nucleation and growth.