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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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
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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.
Kenji Takeuchi, Michael Y. Young, Lawrence E. Hochreiter
Nuclear Science and Engineering | Volume 112 | Number 2 | October 1992 | Pages 170-180
Technical Paper | doi.org/10.13182/NSE112-170
Articles are hosted by Taylor and Francis Online.
Wallis’ flooding correlation is generalized for both small and large pipes by the use of the critical Kutateladze number. A drift flux correlation is then obtained that is tangential to the generalized flooding curve. A simple function of void fraction for the correlation parameter is sufficient to provide good agreement with steam generator test data, without using flow regime maps. After the drift flux correlation is determined with the large-pipe test, it is implemented in the TRAC-PD2 computer code to be tested against the flooding curve for a small-diameter pipe. The Chexal-Lellouche formulas are also applied to the data analysis, and the results are compared with the present correlations. Discussion is extended to the Zuber-Findlay method of data analyses for the drift velocity and the distribution parameter, in relation to the flooding curve.