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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.
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.A. Causey, K.L. Wilson, W.R Wampler, B.L. Doyle
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1585-1588
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29567
Articles are hosted by Taylor and Francis Online.
For the next generation of fusion reactors, tritium inventory will be one of the greatest safety concerns. Both CIT and ITER call for the use of graphite or carbon composites as the first wall and divertor material. If this graphite should contain a large number of traps for the storage of tritium, the resulting inventory could restrict the operation of the reactor. This report presents the results of an experimental study on the effects of neutron irradiation on the trapping of tritium in graphite. Enhancements in the trapping levels by two orders of magnitude up to as high as 0.2 atomic percent were seen for graphite samples irradiated to approximately 10 dpa at different temperatures. The results are compared to those obtained for ion damaged samples. The implications of the results for the operation of CIT and ITER are examined.
