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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.
Ronald D. Boyd, Xiaowei Meng
Fusion Science and Technology | Volume 29 | Number 4 | July 1996 | Pages 459-467
Technical Paper | Blanket Engineeringy | doi.org/10.13182/FST96-A30690
Articles are hosted by Taylor and Francis Online.
Several existing heat transfer models for uniformly heated channels were examined to accurately represent the boiling curve and to characterize the local heat transfer coefficient under high-heat-flux (HHF) conditions. Comparisons with HHF data showed that major correlation modifications were needed in the subcooled partial nucleate boiling (SPNB) region. Because the slope of the boiling curve in this region is important to ensure continuity of the HHF trends into the fully developed boiling region and up to the critical heat flux, accurate characterization in the SPNB region is essential Approximations for the asymptotic limits for the SPNB region have been obtained and have been used to develop an improved composite correlation. The developed correlation has been compared with 363 water data points. For the local heat transfer coefficient and wall temperature, the overall percent standard deviations with respect to the data were 19 and 3%, respectively, for the high-velocity water data.