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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
M. Yoshinuma, K. Ida, M. Yokoyama, M. Osakabe, K. Nagaoka, S. Morita, M. Goto, N. Tamura, C. Suzuki, S. Yoshimura, H. Funaba, Y. Takeiri, K. Ikeda, K. Tsumori, O. Kaneko, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 103-112
Chapter 3. Confinement and Transport | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10797
Articles are hosted by Taylor and Francis Online.
Spontaneous toroidal flow driven by ion temperature gradient and extreme hollow profile of carbon impurity (denoted as an "impurity hole") is observed associated with the increase of ion temperature gradient in the large helical device (LHD). Spontaneous toroidal flows driven by radial electric field and ion temperature gradient are studied. The positive radial electric field drives spontaneous flow in the counterdirection at the plasma edge and in the codirection near the magnetic axis. The component of the spontaneous toroidal flow driven by ion temperature gradient is clearly observed and expected to be one of the dominant components of toroidal flows in the high-ion temperature discharges in LHD. The transport analysis of the carbon impurity in the discharge with impurity hole reveals a low diffusion coefficient and the outward convection velocity, whereas the inward convection is predicted by the neoclassical theory at half the minor radius.