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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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Latest News
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.
I. Tazhibayeva, I. Lyublinski, A. Vertkov, V. Lazarev, E. Azizov, G. Mazzitelli, P. Agostini
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 554-557
Blanket Design and Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12441
Articles are hosted by Taylor and Francis Online.
The objective of this work is to carry out the tests of the KTM tokamak lithium divertor model as well as develop recommendations on the use of lithium technologies in tokamak-reactors. Li-technology will be developed and a Na-K cooled KTM tokamak lithium divertor module will be designed and tested as a result of the project completion. It will be possible to operate the renewed lithium surface module under specific heat loads from 2 to 10 MW/m2 while in a quasi-stationary mode, discharge duration of up to ~5 s. The technical project proposal; design scheme and sketches; and procedure development for preparation, protection, cleaning and rehabilitation of lithium CPS (capillary-porous system) surfaces in tokamak conditions have been completed. The design substantiation calculations; technique development for lithium handling in tokamak conditions; and confirming experiments on T-11M tokamak to prove the procedures developed are still in a progress. The study of both the lithium influence on the KTM plasma discharge parameters and specific power load on the plasma facing components as well as the selection of optimum operational modes of the lithium divertor will be accomplished after completion of the start-up and adjustment tests of the KTM tokamak divertor demonstration models.
