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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Fusion Science and Technology
Latest News
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.
Dennis J. Strickler, Steven P. Hirshman, Donald A. Spong, Michael J. Cole, James F. Lyon, Bradley E. Nelson, David E. Williamson, Andrew S. Ware
Fusion Science and Technology | Volume 45 | Number 1 | January 2004 | Pages 15-26
Technical Paper | doi.org/10.13182/FST04-A421
Articles are hosted by Taylor and Francis Online.
A compact quasi-poloidally symmetric stellarator (QPS) plasma and coil configuration is described that has desirable physics properties and engineering feasibility with a very low aspect ratio plasma bounded by good magnetic flux surfaces both in vacuum and at <> = 2%. The plasma is robust with respect to variations of pressure and the resulting bootstrap current, which leave the bounding flux surface approximately unchanged and thus reduce active positional control requirements. This configuration was developed by reconfiguring the QPS modular coils and applying a new computational method that maximizes the volume of good (integrable) vacuum flux surfaces as a measure of robustness. The stellarator plasma and coil design code STELLOPT is used to vary the coil geometry to determine the plasma geometry and profiles that optimize plasma performance with respect to neoclassical transport, infinite-n ballooning stability up to <> = 2%, and coil engineering parameters. The normal component of the vacuum magnetic field is simultaneously minimized at the full-beta plasma boundary.