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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
J. A. Leuer, S. Ejima, F. J. Helton, J. C. Wesley
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1676-1681
Magnet Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40001
Articles are hosted by Taylor and Francis Online.
A conceptual design of a poloidal field coil system for an ignition and long pulse burn experiment is presented. The coil is located internal to the toroidal field coil and immediately adjacent to the plasma chamber. The advantages this system offers over alternate designs are: sufficient volt-sec to initiate and sustain plasma current for a 300 sec burn, plasma configurations with MHD beta limits in excess of 10%, and the operational flexibility to accommodate a number of different plasma configurations including diverted discharges. For equal ignition margin a divertor configuration requires a larger toroidal field and lower plasma current than a limiter configuration. Power requirements are modest, and technology developments required for construction are within the present state-of-the-art.