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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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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.
J. Appel and B. Roos
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 201-213
Technical Paper | doi.org/10.13182/NSE68-A21086
Articles are hosted by Taylor and Francis Online.
An exact formulation is presented for the release of metallic fission products. Such radioactive atoms are created through fission processes inside the kernel of fuel particles. They can diffuse through the coating of a fuel particle and the surrounding charcoal matrix into the structural graphite of the reactor core. Some atoms traverse this graphite along internal surfaces and finally enter the coolant gas. To find the number of radioactive atoms released into the coolant gas, the diffusion equation in one space dimension is solved numerically taking into account as driving forces both the gradient of the chemical potential and that of the temperature field. The chemical potential is determined respectively by the Langmuir and Freundlich adsorption isotherms for small and large concentrations of metal atoms adsorbed at the highly active internal surfaces of charcoal and graphite. As an example, a parameter study of the release is presented for the most danagerous radioactive metallic isotope, 90Sr. The calculation of the release rate from a single fuel particle shows that the coating does not act as an effective diffusion barrier in this case. It is found that the structural graphite governs the release by virtue of its good adsorptive properties and its low diffusion constant. The results for the concentration profile, the mass current (or flux), and the release of 90Sr are highly sensitive to experimental information on diffusion and adsorption coefficients, in part because of the temperature-activated nature of adsorption and diffusion processes. Since the experimental variables are known with limited accuracy only, a parameter study of the 90Sr release is carried out, that is centered around the best available empirical values for diffusion and adsorption coefficients.