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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.
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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
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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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.
Folco Casadei, Mario Dalle Donne+
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 43-69
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33326
Articles are hosted by Taylor and Francis Online.
The coolant flow across the perforated dip-plate during a hypothetical core disruptive accident in a liquid-metal fast breeder reactor was simulated in a one-dimensional model. Several experiments with water as fluid and with various perforation ratios of the dip-plate and different initial heights of the fluid head over the dip-plate were run. The pressure drop across the dip-plate and the forces acting on the dipplate and on the upper plug of the reactor vessel were measured in a wide range of Reynolds and Strouhal numbers and of an acceleration parameter. The flow pattern downstream from the perforated plate was filmed with a high-speed camera. The resistance coefficients for the transient flow of the coolant through the perforated plate were obtained as a function of the acceleration. The forces acting on the upper plug and their time integral were compared with those acting on the dip-plate. Finally, using highspeed film pictures, the formation of fluid jets downstream from the dip-plate was investigated.