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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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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
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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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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.
G. Saibene, R. Sartori, F. Reiter
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 808-815
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25234
Articles are hosted by Taylor and Francis Online.
The transport of tritium in liquid Pb-17Li has been investigated for different types of capsules and different methods of tritium extraction. Equations describing the tritium release process have been set up and solved, and time-dependent expressions of the outcoming tritium flux have been derived for closed capsules containing stagnant or moving Pb-17Li and for capsules where a He + 0.1% H2 flush gas sweeps the gas phase above the liquid Pb-17Li or bubbles through it. The analytical expressions of the outcoming tritium fluxes depend on tritium diffusivities and solubilities in Pb-17Li and in the container material and on the tritium generation rate in Pb-17Li. The models allow the determination of the characteristic tritium release times when these input parameters are available. The parameters, on the other hand, can be determined by fitting the experimental tritium release data with the theoretical flux equations. The characteristic tritium release time (time to reach 63.2% of the steady state tritium flux) is 14000 s, 7200 s, 2000 s and less than 100 s for the closed stagnant, closed convective, swept and bubbled capsule, respectively, and for the specific conditions of the “Libretto” experiment (Petten - NL).