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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.
R. W. Dunlap and T. D. Gulden
Nuclear Science and Engineering | Volume 32 | Number 3 | June 1968 | Pages 407-416
Technical Paper | doi.org/10.13182/NSE68-A20223
Articles are hosted by Taylor and Francis Online.
A parametric study of a two-zone diffusion model has been performed to describe in-pile diffusion-controlled release of fission products from spherical coated fuel particles. Both the steady-state release and the times to reach steady state are considered. The effects of variations in diffusion coefficients of the fuel and coating, coating thickness, partition coefficient at the fuel-coating interface, contamination fraction, and decay constant have been considered. The results predict three regimes of release for different ranges of half-life and diffusion coefficients. Certain very long-lived isotopes will have high equilibrium release rates controlled by diffusion in the fuel core but probably will not come to equilibrium during the lifetime of a fuel particle. The release of many isotopes with intermediate half-lives is controlled by diffusion in the coating material. Equilibrium release rates in this range are large and probably will be achieved in practice for pyrolytic carbon coated fuel particles. The release of the inert gases is controlled by the level of fuel contamination in the coating material. The beneficial effects of using improved barrier coatings are discussed in terms of the diffusion model. Certain unusual aspects of the in-pile release of fission gases are explained in terms of the results of this model.