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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Jayan K. George, Jagdeep B. Doshi
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 338-349
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35016
Articles are hosted by Taylor and Francis Online.
The pressure disturbance propagation through a weakly compressible medium, bound by rigid structure as well as material interfaces, has an important bearing on the safety analysis of liquid-metal-cooled fast breeder reactors. The analyses have been carried out using numerical algorithms based on Eulerian, Lagrangian, or mixed formulations. Even though the results obtained from these schemes compared well with the benchmark experimental results, certain drawbacks, such as less accurate treatment of material interfaces in the Eulerian schemes and mesh distortion in the La-grangian schemes, and so forth, remain. These drawbacks may be overcome by using a method of characteristics in two dimensions known as the near-characteristic method to solve the problem. The region of interest is discretized into Eulerian grids, and the flow parameters are obtained from the compatibility equations corresponding to the near characteristics generated from the grid points. The material interfaces are tracked explicitly, using the near-characteristic scheme. The scheme is used to analyze a typical core disruptive accident problem, and the results are compared with experimental results as well as those ob. tained using two other numerical schemes. Good agreement is observed among the results; indeed, the one-dimensional problem of exploding wire phenomena and the two-dimensional problem of core disruptive accident analysis validate the effectiveness of the scheme. The future extension of the present scheme will include fluid structure interaction and complex internal structures.