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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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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.
G. Nash
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 13-20
Technical Paper | Reactor | doi.org/10.13182/NT80-A32551
Articles are hosted by Taylor and Francis Online.
Measurements of steam bubble velocities and voidage have been made in the relatively small Core B of the Lingen boiling water reactor. The results of axial scanning in one radial position have produced experimental values of slip ratio, power (from a traveling in-core probe), voidage, and coolant mean density over the core height for this position. This one set of distributions has enabled us to test current U.K. Atomic Energy Authority (UKAEA) models of subcooled boiling and slip ratio against experiment. From the comparisons, it appears that we can predict the onset of voiding well. Of four slip options tested, the current one used by UKAEA computer codes HAMBO and JOSHUA (Bankoff-Jones) predicts too high a slip ratio. A closer fit to experiment comes from the new Bryce flow-dependent slip option. Any changes in the modeling must be checked, however, with coupled thermal-hydraulics/neutronics computations.
