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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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.
H. F. Poppendiek, L. D. Palmer
Nuclear Science and Engineering | Volume 3 | Number 1 | January 1958 | Pages 85-106
Technical Paper | doi.org/10.13182/NSE58-A25449
Articles are hosted by Taylor and Francis Online.
Radial temperature distributions within the cores of heterogeneous circulating-fuel reactors having elementary channel and circular pipe geometries are described mathematically; uniform and nonuniform radial volume-heat-source distributions are considered. Solutions for cores with uniform volume-heat source distributions are tabulated so that detailed radial temperature profiles can be determined within fuels which are being uniformly cooled at the core walls. A derivation is presented which describes the heat transfer within a reactor core when walls are being non-uniformly cooled along its length; volume heat sources also exist within the core walls and coolant.