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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.
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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
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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.
D. S. Rowe, D. E. McFeron
Nuclear Science and Engineering | Volume 26 | Number 3 | November 1966 | Pages 319-328
Technical Paper | doi.org/10.13182/NSE66-A17352
Articles are hosted by Taylor and Francis Online.
This paper presents a mathematical model that describes the heat transfer in a defectively bonded flat-plate fuel element. The bond defect is assumed to exist only on one side of the fuel plate and to be either a circular spot or infinite strip in shape. Details of the general solution to the heat conduction equation for the mathematical model are shown for the strip-type defect. For a particular type of defect, the temperature distribution is dependent upon three dimensionless parameters that include the effects of defect size and the heat transfer properties of the defective fuel element. Data are provided in terms of the three dimensionless parameters that permit rapid estimates of fuel temperatures in fuel plates with strip and spot defects. These defects are assumed to be step reductions in the normal fuel-boundary conductance. Defect sizes on the order of a couple of fuel thicknesses can cause significant local increases in the fuel temperature and fuel-surface heat flux.