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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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.
M. S. Tillack, D. K. Sze, M. A. Abdou
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1088-1096
Nuclear Technology Experiments and Facilities | doi.org/10.13182/FST86-A24878
Articles are hosted by Taylor and Francis Online.
The lack of experimental data for liquid metal blankets in the fusion environment restricts our ability to develop designs with demonstrated feasibility and adequately characterized performance. In order to confidently predict neutronic and thermal hydraulic performance of blankets, a variety of experiments will be needed. Ultimately, verification of all nuclear components will require testing in a fusion environment. However, a great deal of information can be obtained prior to fusion testing using non-neutron facilities to explore separate, multiple, and partially integrated effects. A large class of issues which can be effectively studied in a non-neutron environment are those impacted by MHD transport phenomena. A coordinated test program is described below to treat momentum, heat, and mass transport issues for liquid metal blankets.