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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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
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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
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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.
K. Nagaoka, Y. Takeiri, S. Morita, K. Ida, M. Yokoyama, M. Yoshinuma, H. Funaba, S. Murakami, T. Minami, K. Tanaka, T. Ido, A. Shimizu, K. Ikeda, M. Osakabe, K. Tsumori, O. Kaneko, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 46-52
Chapter 3. Confinement and Transport | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST58-46
Articles are hosted by Taylor and Francis Online.
Ion heating experiments have been intensively carried out in high- and low-Zeff conditions of Large Helical Device plasmas. In high-Zeff plasmas utilizing neon or argon gus puffing, the ion heating power normalized by ion density (Pi /ni) increases with ZeffL and the central ion temperature increases with Pi /ni without saturation. The central ion temperature of 13.5 kV was achieved in an argon-seeded plasma, strongly suggesting the capability of the helical configuration to confine high-performance plasmas. In low-Zeff experiments, improvement of ion heat transport was realized in the core plasmas heated by high-power neutral beam injections. The ion temperature has a peaked profile with steep gradient in the core region (ion internal transport barrier). The transport analysis indicates that the anomalous transport is reduced in the core region, where the negative radial electric field is predicted by the neoclassical ambipolarity. Improvement of ion heat transport with positive radial electric field was also successfully demonstrated utilizing strongly focused electron cyclotron resonant heating, suggesting further improvement of ion heat transport in reactor-relevant plasmas.