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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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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.
D. C. Lousteau, J. N. Herndon, F. C. Davis, S. L. Schrock
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1389-1396
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST92-A29917
Articles are hosted by Taylor and Francis Online.
During the Conceptual Design Activity (CDA) for the International Thermonuclear Experimental Reactor (ITER), a tokamak reactor design was established that emphasized performance of the individual systems in a minimum overall reactor and building size. The resulting high component density arrangement dictates careful attention to assembly and maintenance (A&M) considerations in the development of the configuration. The A&M task is complicated further because remote maintenance techniques will be required in many areas of ITER after the start of deuterium-tritium operations. During die CDA, the ITER design team addressed many aspects of an overall A&M system. This paper discusses the ITER A&M philosophy that evolved, describes the ITER configuration as it relates to maintenance, and describes the procedures and equipment required for specific maintenance operations. Remote replacement of the in-vessel divertors and blanket/shield modules is discussed in detail. In addition, research and development needs for key enabling technology are addressed.