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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
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.
Gennadij T. Razdobarin, Eugene E. Mukhin, Vladimir V. Semenov
Fusion Science and Technology | Volume 35 | Number 1 | January 1999 | Pages 389-392
Poster Presentations | doi.org/10.13182/FST99-A11963891
Articles are hosted by Taylor and Francis Online.
ITER divertor operation is dominated by the necessity to exhaust around 200MW power via the scrape-off layer. A large fraction of the input power must be irradiated by the impurities either intrinsic or seeded. It is important that the radiation source be well distributed over the entire divertor plasma. The plasma detachment at the divertor target should be precisely adjusted as to enable a partially attached operating, that is detached near the separatrix strike point and attached further out in the scrape-off layer. To provide information on key fenomena which may limit the divertor performance is the challenging task for diagnostics in ITER.
The reliable Tc, nc profile measurements in the divertor upstream (near X-point) and downstream (divertor bottom) regions address the highly promising Thomson scattering diagnostics. The high resolution time-of-flight LIDAR Thomson scattering for the X-point and the conventional Thomson scattering technique for the divertor leg fit the reference divertor configuration with minimal impact on ITER design.