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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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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.
S. M. Ghiaasiaan, J. R. Muller, D. L. Sadowski, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 229-238
Technical Paper | doi.org/10.13182/NSE97-A24476
Articles are hosted by Taylor and Francis Online.
Critical discharge of highly subcooled water through a cylindrical channel with a 0.78-mm inside diameter and 0.78 mm in length was experimentally studied. The range of the initial water subcooling was 76 to 200 K, and the initial water pressure was in the range 0.5 to 5.2 MPa. The measured critical mass fluxes were compared with three models appropriate for application to critical flow in small and short channels.The experimental results confirm the significant effect of pressure losses on critical discharge rates in small channels. They indicate, however, that the frictional pressure losses in cracks may be considerably larger than losses predicted by the widely used correlations for rough channels. It is shown that models and correlations based on isentropic homogeneous equilibrium flow in the channel accurately predict the critical flow data, provided that the liquid initial stagnation pressure is adequately corrected for the channel entrance pressure loss.