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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. Primak, L. H. Fuchs
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 49-56
doi.org/10.13182/NSE57-A15572
Articles are hosted by Taylor and Francis Online.
A method for using a saturating property to formulate a linear dosage scale is developed. The method is applied to the determination of the radiation damage rate for graphite in a nuclear reactor using the per cent decrease in electrical conductivity as the property. The damage rates in a number of irradiation facilities of the CP-3, CP-3′, and X-10 reactors are given. It is conclusively shown that the thermal neutron flux cannot be used to indicate the damage rate, for the one can be varied by more than an order of magnitude with respect to the other.
