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Division Spotlight
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.
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.
R. H. Chen, M. L. Corradini, G. H. Su, S. Z. Qiu
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE12-10
Articles are hosted by Taylor and Francis Online.
A molten fuel breakup model that considers solidification effects is proposed in this paper. Both the effect of a solid crust layer and the effect of thermal stresses on the fuel particle fragmentation are taken into account in this model. This solidification model predicts the transient temperature profile and crust layer thickness of the fuel particle by numerically solving the Fourier heat conduction equation under specific initial and boundary conditions. This fuel particle breakup model and transient temperature profile model were incorporated into the TEXAS fuel-coolant interaction (FCI) model; this revised TEXAS FCI model is called TEXAS-VI. This paper compares TEXAS-VI to the FARO L14 experiment (FARO L14), for which fuel-coolant mixing and quench data have been published. The FARO L14 pressure history, liquid water pool temperature, and vapor temperature were found to be in good agreement with the revised model predictions. This mixing behavior will also have an impact on FCI explosion energetics. The solidification effect is under investigation for energetics.