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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
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
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
Ehsan U. Khan
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 112-115
Technical Note | doi.org/10.13182/NSE76-A28467
Articles are hosted by Taylor and Francis Online.
The relative importance of energy redistribution by thermal conduction and sweep flow mixing in a wire-wrapped fuel assembly are quantitatively described at various Reynolds numbers. For a given bundle geometry, a critical Reynolds number exists below which thermal conduction appears to govern the temperature distribution within the bundle. As the thermal conduction effects become progressively important at low Reynolds numbers, the transverse temperature gradient in the bundle decreases. This result would have an important effect on incoherency in assembly voiding. If one were to develop a model of a full-size liquid-metal fast breeder reactor bundle to study incoherency in voiding, an important parameter is the maximum temperature difference at the bundle exit. Whereas this parameter is the same for a 19- and 217-pin bundle at design operating conditions, it is significantly different at low Reynolds numbers. This low Reynolds number bundle-size effect was determined by analysis of steady-state data and is valid for very slow transients where the thermal inertia of the structure is unimportant. Inclusion of the structure thermal inertia would tend to diminish this bundle-size effect.