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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Ashwin P. Muzumdar, Douglas G. Andrews
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 275-280
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33574
Articles are hosted by Taylor and Francis Online.
A semi-analytical/empirical relationship has been developed to describe the axial flux variation in one dimension in a nuclear reactor when the local reactivity indicator k∞ is an explicit function of the neutron flux. This relationship is valid over a wide range and correlates well with the results produced by other methods. This relationship expresses in a single explicit equation the excess reactivity as a function of the fuel cycle time, axial flux form factor, and neutron leakage.