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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
Alan J. Markworth
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 506-507
Technical Notes | doi.org/10.13182/NSE72-A22570
Articles are hosted by Taylor and Francis Online.
A simple model for the gas-diffusion-controlled growth of stationary gas bubbles in an isothermal solid, under constant rate of gas generation, is used to evaluate the temperature dependence of fission-gas swelling in uranium monocarbide. Using experimental data for the temperature-dependent volume diffusivity of xenon in uranium carbide, it is found that the predicted temperature at which the onset of fission-gas swelling occurs, evaluated at a given fission density, correlates relatively well with swelling data and is of the order of one-half the absolute melting point. Variations of bubble concentration and gas-generation rate are found to affect this predicted swelling-onset temperature only to a relatively slight extent.