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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
B. A. Nelson, T. R. Jarboe, D. J. Orvis, A. K. Martin, J. Xie, C. Zhang, L. Zhou
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 333-336
Compact Torus (Field-Reversed Configuration, Spheromak) Concepts | doi.org/10.13182/FST95-A11947099
Articles are hosted by Taylor and Francis Online.
Coaxial helicity injection is used to form and sustain low aspect ratio tokamaks at currents of up to 250 kA in the Helicity Injected Tokamak experiment. Plasma currents can be sustained at an average of 225 kA for 2 ms, with on axis electron thermal energies up to 80 eV, or for longer times, 140 kA average for 7 ms, many resistive diffusion times. Spectroscopic measurements of the higher current discharges suggest burn-through of oxygen impurities. These plasmas have a rotating n = 1 distortion, appearing only on the outer, bad-curvature region. Equilibria reconstruction, fitting to experimental data, shows tokamak q profiles achieved with hollow plasma current profiles.