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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
R. L. Boivin, J. L. Luxon, M. E. Austin, N. H. Brooks, K. H. Burrell, E. J. Doyle, M. E. Fenstermacher, D. S. Gray, M. Groth, C.-L. Hsieh, R. J. Jayakumar, G. R. McKee, C. J. Lasnier, A. W. Leonard, R. A. Moyer, T. L. Rhodes, J. C. Rost, D. L. Rudakov, M. J. Schaffer, E. J. Strait, D. M. Thomas, M. Van Zeeland, J. G. Watkins, G. W. Watson, W. P. West, C. P. C. Wong
Fusion Science and Technology | Volume 48 | Number 2 | October 2005 | Pages 834-851
Technical Paper | DIII-D Tokamak | doi.org/10.13182/FST05-A1043
Articles are hosted by Taylor and Francis Online.
The DIII-D tokamak, located at General Atomics in San Diego, California, has long been recognized as being one of the best diagnosed magnetic fusion experiments. Composed of more than 50 individual systems, the diagnostic set takes advantage of a high number of large-aperture access ports. These instruments are used in support of basic control of the tokamak and experiments in the transport, stability, boundary and heating, and current drive science areas. These systems have contributed to the success of the Advanced Tokamak program, in addition to the many contributions to our physics understanding and real-time control of fusion-relevant plasmas. Numerous novel techniques have been developed, tested, and fielded on DIII-D including new approaches required for a burning plasma experiment. Details of the diagnostic systems will be described along with some illustrative recent results.