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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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.
Mario Dalle Donne*, Giacinto P. Tartaglia†
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 298-325
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33843
Articles are hosted by Taylor and Francis Online.
The multiphase coolant flow across the perforated immersion plate during a hypothetical core disruptive accident in a liquid-metal fast breeder reactor was simulated in a one-dimensional model. Extending from previous work with one-phase flow, water-air mixtures were used to test two-phase behavior. A large experimental matrix included systematic variation of the following parameters: geometry of the immersion plate (perforation ratio, number of the holes), height of the fluid head over the immersion plate, air volume fraction, size of the air bubbles, and acceleration of the fluid. The pressure drop across the immersion plate, the forces acting on the immersion plate and on the upper plate, acceleration and displacement of the piston, the air volume fraction, and the size of the air bubbles were measured in a wide range of Strouhal and acceleration numbers. The flow pattern downstream of the immersion plate was filmed with a high- speed camera. The following correlations were investigated: