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
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
IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
Ralph Ewig, Thomas R. Jarboe
Fusion Science and Technology | Volume 36 | Number 1 | July 1999 | Pages 62-68
Technical Paper | doi.org/10.13182/FST99-A92
Articles are hosted by Taylor and Francis Online.
A method for modeling the time-varying magnetic geometry in a low-aspect-ratio tokamak is developed. The model includes mutual inductance effects of an arbitrarily shaped (toroidally symmetric) conducting shell, poloidal field (PF) coils, a saddle coil with finite gap resistance, and a single element, distributed plasma current. The plasma current distribution is specified using EFIT results and remains unchanged during the simulation, while the magnitude of the plasma current is ramped up linearly over time. The resulting simulation code is used to predict power supply requirements and tracking capabilities of an arbitrarily chosen feedback mechanism employed to operate the PF coils of the tokamak.