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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
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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.
Hermann WÜrz, Nicolai Arkhipov, Vitali Bakhtin, Boris Bazylev, Igor Landman, Valeri Safronov, Dima Toporkov, Sergej Vasenin, Anatoli Zhitlukhin
Fusion Science and Technology | Volume 32 | Number 1 | August 1997 | Pages 45-74
Technical Paper | First-Wall Technology | doi.org/10.13182/FST97-A19879
Articles are hosted by Taylor and Francis Online.
In evaluating the lifetime of plasma-facing components for the International Thermonuclear Experimental Reactor (ITER) against nonnormal high heat loads, credit is taken from the existence of a plasma shield that protects the target from excessive evaporation. Formation and physical properties of plasma shields are studied at the dual plasma gun facility, 2MK-200, under conditions simulating ITER hard disruptions and edge-localized modes (ELMs). The experimental results are used for validation of the theoretical modeling of the plasma/surface interaction. The important features of the non-local thermodynamic equilibrium plasma shield, such as temperature and density distribution, its evolution, the conversion efficiency of the energy of the plasma stream into total and soft X-ray radiation from highly ionized evaporated target material, and the energy balance in the plasma shield, are reproduced quite well. Thus, realistic modeling of ITER disruptive plasma/wall interaction is now possible. Because of the rather small target erosion in the simulation experiments, material erosion for ITER typical disruptions and ELMs cannot be evaluated from these simulation experiments. This requires additional simulation experiments with hot plasma streams of longer pulse duration and a separate numerical analysis, which can now be performed with validated theoretical models.