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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
R. Sakamoto, H. Yamada, M. Kobayashi, J. Miyazawa, S. Ohdachi, T. Morisaki, S. Masuzaki, M. Goto, H. Funaba, I. Yamada, K. Ida, S. Morita, B. J. Peterson, N. Ohyabu, A. Komori, O. Motojima, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 53-60
Chapter 3. Confinement and Transport | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10793
Articles are hosted by Taylor and Francis Online.
An interesting high-density operational regime with an internal diffusion barrier (IDB) has been extended to the helical divertor configuration in the Large Helical Device. The IDB is characterized by steep density gradient in core plasma and the attainable central density exceeds 1 × 1021 m-3 at the moderate magnetic field [approximately]2.5 T while keeping relatively low density mantle plasma surrounding the core. In the IDB discharge, significant central pressure rise is observed, and the maximum central pressure attains 150 kPa by optimizing magnetic configuration. Such a high central pressure causes very large Shafranov shift, more than half radius, even at high magnetic field. Core fueling is absolutely essential for the IDB formation, and the IDB is reproducibly obtained by employing intensive multiple-pellet injections. The attainable density is restricted by lack of heat deposition at core plasma due to strong attenuation of a neutral beam in the high-density plasma.