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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Latest News
Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
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.
