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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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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.
C. J. Murphy, P. M. Anderson, C. J. Lasnier
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 539-543
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | doi.org/10.13182/FST07-A1544
Articles are hosted by Taylor and Francis Online.
The lower divertor of the DIII-D tokamak has been modified to provide improved density control of the tokamak plasma during operation in a high triangularity double-null configuration. Union Carbide ATJ grade graphite tiles covering the new lower divertor and vessel floor were designed to have better tile-to-tile alignment and to withstand higher heat flux than existing tiles.Gaps between tiles were successfully reduced from 2.5 to 0.4 mm and tile top surface alignment was greatly improved from 1.0 to 0.1 mm. Small tile gaps along with good vertical edge alignment greatly reduce the number and size of thin edges visible to the plasma, thus minimizing possible carbon introduction into the plasma. Close tile-to-tile alignment was the result of the very flat divertor plate surface, carefully controlled tile positioning, well-machined graphite tiles, and hand filing.Tiles were specified to survive 27 MJ of energy deposited per toroidal row of tiles during a 10 s shot period. When this energy is applied over the narrow triangular heat flux profiles originally specified, modeling shows that the tiles exceed maximum allowable tensile stress. Modeling does show that the tiles are able to absorb the 27 MJ per row without exceeding stress limits in cases where the heat flux profile is less focused than the original design specification.This paper will compare tile design analysis with operational experience obtained during the first 12-week operations campaign with the new divertor.