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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
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
D C Robinson
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 144-149
Overview Paper | doi.org/10.13182/FST95-A11947059
Articles are hosted by Taylor and Francis Online.
The small aspect ratio tokamak combines the attractive features of the tokamak, reverse field pinch and spheromak to produce a compact, stable, high-β configuration with low external fields. Experiments on the Small Tight Aspect Ratio Tokamak (START) at Culham have demonstrated the production of stable, high temperature (Te ≤ 1keV), naturally elongated plasmas with good confinement, at aspect ratios down to 1.25. These plasmas are, so far, free from current-terminating disruptions and exhibit a natural divertor action. Theoretical studies have demonstrated robust stability at high β (> 30%) and self-consistent steady-state equilibria using pressure and beam driven currents. Such steady-state solutions exist for devices at the Mega Amp level, compact component test facilities and fusion power plants of modest size (Ro~2–3m).