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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.
T. K. Larson, R. A. Dimenna
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 21-32
Technical Paper | doi.org/10.13182/NSE88-A29011
Articles are hosted by Taylor and Francis Online.
Preservation of similitude criteria in current mathematical models used for transient analysis of thermal-hydraulic systems is discussed. Input models for the RELAP5 computer code were developed at the Idaho National Engineering Laboratory for two simple hypothetical natural circulation systems consisting of a closed loop containing energy generation, energy removal, and flow resistance. The two models differed significantly in geometric scale size. A reference model had components and operating conditions in a range similar to those found in typical nuclear steam supply systems; a scaled model, geometrically much smaller than the reference model, had components that were sized from the reference model using similarity criteria presented in the literature. Steady-state and transient single- and two-phase natural circulation calculations were conducted using both models to determine if the model-to-model relationships in time, pressure drop, and velocity scales were in accordance with the similitude criteria. Results indicate that, while the code predicts the expected fundamental effects of geometric scale, there are noteworthy differences in the details of calculations.