ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Charles R. Marotta
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 420-422
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33927
Articles are hosted by Taylor and Francis Online.
A simple calculational method is developed that can quickly and accurately estimate total control rod worth for a class of reactors possessing fuel/control channel symmetry throughout its core. The movable, nonfissionable, poisoned control channel has identical neutron absorption and scattering properties and geometry similar to the fuel channels. Hexagonal lattices employed in fast breeder and graphite-moderated thermal reactors possess the necessary fuel/control lattice symmetry with spectrally innocuous coolants for both channels (sodium or helium both for fast and thermal systems) required to apply the method. The number of fuel and control channels is the parameter determining control worth and is tantamount to estimating by inspection. It is applied to eight fast sodium-cooled reactors and four thermal-, sodium-, or helium-cooled, graphite-moderated reactors. The Δk/k estimated worths are generally better than ±20% plant values.