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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Ronald F. Schmitt
Fusion Science and Technology | Volume 57 | Number 2 | February 2010 | Pages 152-161
Technical Paper | doi.org/10.13182/FST10-A9369
Articles are hosted by Taylor and Francis Online.
Two new methods for designing modular stellarator coils are presented. Stellarator coils provide necessary magnetic field to produce the plasma shape for a desired magnetohydrodynamic (MHD) equilibrium. The methods optimize a continuous current on a surface - i.e., coil current is represented by a continuous-current sheet on a toroidal winding surface - and the process of coil cutting is not addressed. In contrast to previously published continuous-current methods that optimize coil current by minimizing the flux at the plasma boundary, the new methods presented in this paper search for optimal solutions by minimizing the displacement of the plasma boundary, i.e., the last closed magnetic surface. The physical displacement of the plasma boundary is computed from the magnetic field normal using linear MHD perturbation theory. A comparison with two similar continuous-current codes is given in terms of both methodology and results. The new codes show modest improvement over previously published continuous-current codes.