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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.
M. Zucchetti, B. Coppi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2017-2022
Safety, Recycling, and Waste Management | doi.org/10.13182/FST92-A30017
Articles are hosted by Taylor and Francis Online.
A study on the activation of the Ignitor machine is performed. The machine has been modelled with the neutron transport code ANISN, in orderto calculate the neutron fluxes. These have been input in the inventory code ANITA, and the neutron-induced radioactivity in the structures of the machine is obtained. It becomes clear that the activation of certain parts of the machine (vessel, magnets) requires the adoption of remote handling equipment for their maintenance. The substitution of INCONEL 625 (vessel material for Ignitor) by a material with lower long-term activation is discussed.
