ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
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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.
C. E. Winters
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 443-447
Technical Paper | doi.org/10.13182/NSE63-A17396
Articles are hosted by Taylor and Francis Online.
The High Flux Isotope Reactor (HFIR), now being constructed at Oak Ridge National Laboratory, was designed for almost the single purpose of transmuting elements at the highest possible rate consistent with reasonable extrapolations of proven technology. The reactor is of the fluxtrap type, with a cylindrical core. It is light-water cooled and beryllium reflected. At the design power of 100 Mw the reactor will produce a calculated unperturbed neutron flux of 5 × 1015 neutrons/cm2, sec in the target region. A target of 300 gm of Pu242 for the production of transplutonium elements will reduce this flux to 2 or 3 × 1015.