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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Michael Drevlak
Fusion Science and Technology | Volume 33 | Number 2 | March 1998 | Pages 106-117
Technical Paper | doi.org/10.13182/FST98-A21
Articles are hosted by Taylor and Francis Online.
A method for finding a set of modular, poloidally closed stellarator coils confining a plasma in a given equilibrium configuration is described. The proposed technique performs a direct nonlinear optimization of the coil shapes with respect both to the desired structure of the magnetic field and to geometric constraints required by the fabrication process of the coils. This is in contrast to the method employed successfully for the design of the coil system of experiment W7-X, which divides the minimization of the field error and the adjustment of the geometric coil properties into consecutive steps. The viability of the new method is exemplified by two alternative coil designs for the plasma configuration of W7-X, offering more space inside the coils for installation of the divertor system or a blanket. The results are compared with the original coil configuration designed for W7-X.