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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
K. Almenas
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 22-32
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30944
Articles are hosted by Taylor and Francis Online.
The feasibility of using a nuclear reactor as a thermally radiating energy source is investigated. Design parameters including radiant energy transmission, attenuation of γ and neutron fluxes, criticality, and heat transfer are evaluated. Since conclusive experimental data for nuclear and high temperature heat transfer properties are lacking, a mathematical relationship between these limiting parameters is derived and the results are presented for the whole range over which they are likely to vary. For some of the designs considered, the overlap within which a thermally radiating nuclear reactor can be considered feasible is sufficiently broad to cover all possible uncertainties. It is concluded, therefore, that a spherical W-UO2 cermet shell reactor, operating at a surface temperature of 2800°K, assuming a modest extrapolation of present-day materials technology, is indeed feasible.