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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Fusion Science and Technology
May 2025
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.
Kiyoshi Yatsu, Leonid G. Bruskin, Teruji Cho, Minoru Hamada, Mafumi Hirata, Hitoshi Hojo, Makoto Ichimura, Kameo Ishii, Khairul M. Islam, Akiyoshi Itakura, Isao Katanuma, Yasuhito Kiwamoto, Junko Kohagura, Shigeyuki Kubota, Atsushi Mase, Yousuke Nakashima, Teruo Saito, Yoshiteru Sakamoto, Teruo Tamano, Yoshinori Tatematsu, Tokihiko Tokuzawa, Masayuki Yoshikawa
Fusion Science and Technology | Volume 35 | Number 1 | January 1999 | Pages 52-59
Invited Lectures | doi.org/10.13182/FST99-A11963826
Articles are hosted by Taylor and Francis Online.
Potential confinement of an ICRF-heated high-ion temperature plasma in GAMMA 10 is experimentally studied. The potential confinement was shown from data of one-end plugging and both-end plugging. The waveform of end loss current and an analysis of end loss ion energies have also indicated potential formation and confinement. The central cell line density increases 50% by the potential confinement. Some radial losses were observed in the anchor and/or plug/barrier regions and a rate of the radial loss was measured by using the data from one-end plugging. Under an experimental condition, the radial loss rate was estimated to be about 3%. In order to reduce the radial loss, conducting plates were installed adjacent to the plasma in the anchor transition region. The density increase of 60 % was attained after installation of the conducting plates and a higher density increase can be expected in the near future. The density increase was 50% before installation of the conducting plates. Controllability and reproducibility of the potential confinement are also improved after installation of the conducting plates.