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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.
S. B. Gunst, E. D. McGarry, J. J. Scoville
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 407-418
Technical Paper | doi.org/10.13182/NSE60-A25738
Articles are hosted by Taylor and Francis Online.
Natural uranium dioxide specimens of Shippingport PWR-l blanket-rod geometry are exposed in the Materials Testing Reactor (flux 2 × 1014 n/cm2−sec) and discharged periodically (every three weeks) for measurements in the Reactivity Measurement Facility (RMF). The time-integrated thermal and epithermal fluxes are measured during each exposure cycle, and together with the MTR Daily Power Logs, give the complete exposure history. Measurements in the RMF are used to determine an experimental value for η/η0 (η0 is the preirradiation value) which may be compared with the theoretical η/η0 calculated for the measured exposure history using appropriate neutron-interaction parameters. In the theoretical calculations, the thermal absorption cross section of stable fission products is taken to be 50 barns per fission. Although the experimental and theoretical results are derived completely independently, agreement within 1 % in η/η0 is found for the behavior following all cycles of irradiation comprising exposures from zero to 15,600 Mwd/ton.