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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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
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.
S. Sakakibara, H. Yamada, K. Toi, A. Ejiri, K. Ida, H. Iguchi, K. Matsuoka, T. Minami, T. Morisaki, S. Morita, O. Motojima, K. Narihara, K. Nishimura, S. Okamura, K. Tanaka, J. Xu, I. Yamada, K. Watanabe
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 231-234
Helical Systems | doi.org/10.13182/FST95-A11947076
Articles are hosted by Taylor and Francis Online.
In low density plasmas of CHS, it has been observed that co- direction of neutral beam injection strongly influences the characteristics of MHD mode. The fluctuation level is strongest in all operational regime of CHS plasmas. The effect of beam driven currents on this mode was investigated experimentally from a viewpoint of an interchange mode. The experimental results indicate that the characteristics of this mode strongly depend on the net toroidal current. It suggests that this mode is an ideal interchange mode because of the suppression of the fluctuation level due to the increase in magnetic shear.
