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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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. Bandyopadhyay
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 349-358
Technical Paper | Fuel | doi.org/10.13182/NT78-A32119
Articles are hosted by Taylor and Francis Online.
Direct electrical heating (DEH) experiments have been analyzed to study the fuel and fission gas response to simulated thermal transient conditions in unirradiated UO2 and irradiated mixed-oxide fuels. The results indicate that both fission gas and fuel melting strongly influence the fuel response behavior during transients. The information obtained from the DEH tests has been used to draw a preliminary “fuel response diagram” that contributes to an understanding of such macroscopic fuel behavior as gross fuel swelling and fuel failure as functions of the transient time and heating rate. A comparison of these test results and the trend depicted by the fuel response diagram with results obtained from experiments performed in the transient reactor test facility indicates that certain aspects of fuel behavior during transients can be reasonably simulated by the DEH technique.
