ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
William G. Blessing
Nuclear Science and Engineering | Volume 8 | Number 2 | August 1960 | Pages 105-111
Technical Paper | doi.org/10.13182/NSE60-A25785
Articles are hosted by Taylor and Francis Online.
This article considers the physics calculations required to determine power, heat flux, and burnup for ceramic fuel materials as a function of variables such as fuel radius, enrichment, reactor thermal neutron flux, and irradiation time. I t is demonstrated t h a t high fuel burnups may be obtained using moderate thermal neutron flux by proper choice of variables. Heat transfer calculations utilizing the thermal resistance concept for a specific capsule design are described, together with an analysis of the design and operational uncertainties.
