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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.
Franco Vittorio Frazzoli, Alberto Magrini
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 177-182
Technical Paper | Instrument | doi.org/10.13182/NT79-A32308
Articles are hosted by Taylor and Francis Online.
A neutron gauge for the accurate determination of high mean void fractions in a water-steam mixture has been designed to operate on the transmission of a thermal-neutron beam obtained with a 252Cf neutron source coupled with a polyethylene howitzer. Calibrations, carried out with a Plexiglas-air combination simulating annular flow and core flow, show that the gauge is characterized by high sensitivity and precision with respect to the other radiation techniques. Taking into account the lack of calibration standards and the wide range of water and steam densities generally involved in heat transfer processes, we developed a mathematical model of the gauge response to obtain adequate performances for practical use. The model, which is valid in principle for any flow regime, is specialized here for annular flow, which is of interest for the foreseen application in heat transfer studies on an out-of-pile test facility.