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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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
J. D. Galambos, D. J. Strickler, Y-K. M. Peng, R. L. Reid
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 483-488
Plasma Engineering | doi.org/10.13182/FST89-A39746
Articles are hosted by Taylor and Francis Online.
Trade studies are performed to determine the optimum plasma elongation for a next-step tokamak such as the International Thermonuclear Experimental Reactor. Degradations of the plasma beta limit for high elongations and poloidal field coil scaling with elongation are included in the analysis. When plasma ignition is required using confinement scalings that include direct plasma current or power degradation terms, the optimum elongation is between 2.5 and 2.9, but generally the minimum-cost curve is relatively flat for elongations over 2.3. When confinement scalings that depend only on size are used or when only current drive performance is required, the optimum elongation is near 2.3. Also, when only a plasma current and neutron wall load are used as plasma performance limits, the optimum elongation is between 2.6 and 2.8, but with small cost benefits above elongations of 2.3.