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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.
R. C. Lloyd, E. D. Clayton, C. R. Richey
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 690-697
Technical Paper | doi.org/10.13182/NSE58-A25556
Articles are hosted by Taylor and Francis Online.
The graphite diffusion length was measured as a function of temperature in a 101-inch cube of graphite. A water-cooled BF3 counter was used as the neutron flux detector, with additional measurements being made with gold and indium foils. The steady state neutron flux was furnished by means of four -gram, Ra-Be neutron sources. Measurements were taken over a range of temperature from 22°C to 600°C at intervals of about 50°C. The variation of diffusion length with temperature change is in good agreement with the calculated variation assuming a 1/υ cross section for graphite and a constant transport mean free path.