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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.
M. Nagata, Y. Kinugasa, T. Uyama
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 387-390
Compact Torus (Field-Reversed Configuration, Spheromak) Concepts | doi.org/10.13182/FST95-A11947112
Articles are hosted by Taylor and Francis Online.
A spheromak configuration consisting of bias flux surrounding a core region of closed flux surfaces has been successfully sustained in the Flux Amplification Compact Torus (FACT) device by DC/Coaxial helicity injection. In this experiment, the energy transfer efficiency is estimated to be about 30%. The relaxed configuration posseses a low q profile (1/3<q<1/2) whose shape implies that the current density is concentrated in the core and which is maintained by the process of MHD relaxation. The current conversion and rapid inward diffusion of the injected current is found to be significantly related to the n=1 helical deformation of the open field lines along the geometric axis. In this paper, we present some design parameters for the planned Helicity Injected Spherical Torus (HIST) which will permit a corresponding investigation to the above to be made for a tokamak.