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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.
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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.
E. A. Fischer
Nuclear Science and Engineering | Volume 78 | Number 3 | July 1981 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE81-A20300
Articles are hosted by Taylor and Francis Online.
An approximate method to calculate the parallel neutron leakage in fast reactor slab lattices is described. It is derived from the integral transport equation and assumes isotropic scattering. By using an expansion in terms of oscillating functions, rather than the usual power series expansion in the buckling, it is proven that the method is also valid for voided cells. Results for a two-region cell are presented; they confirm that the widely used Benoist equation is valid for cases when sodium is present. However, for voided or nearly voided cells, the Benoist equation fails, whereas the new method is valid for any cell composition. The same method is applied to find the effective diffusion coefficient for a low-density channel. In the limit of zero buckling, the method reduces to well-known results available in literature by Rowlands. However, the buckling correction, obtained by a consistent expansion of the integral transport equation, is different from similar corrections in the literature.