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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.
K. S. Smith
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 451-458
Technical Paper | doi.org/10.13182/NSE82-A20286
Articles are hosted by Taylor and Francis Online.
An investigation of first-order perturbation (FOP) methods for computing sample worths has been performed. It is demonstrated that conventional cell homogenization methods introduce errors into FOP reactivity calculations because the intracell structure of adjoint fluxes is neglected. These errors are such that the conventional FOP reactivity expression is not accurate to first order, even in the limit of infinitesimal perturbations. A method for avoiding such approximations is introduced and applied to the calculation of small sample worths in plate-type fast reactor critical assemblies. It is demonstrated that errors introduced by real flux weighting of cross sections are such that homogenized FOP reactivity calculations overestimate fissile material worths in several critical assemblies by 5 to 10%. It is shown that these errors arise because of the heterogeneous nature of plate-type critical assemblies, and when appropriate reactivity calculations (which account for spatial heterogeneity of adjoint fluxes) are performed, a significant fraction of the long-standing central worth discrepancy is eliminated.