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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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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.
R. Farhadieh, W. H. Gunther
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 298-306
Technical Paper | Material | doi.org/10.13182/NT80-A32532
Articles are hosted by Taylor and Francis Online.
An experimental study of the downward penetration of molten UO2 into substrate limestone concrete was conducted. Joule heating was used to melt the UO2. The technique allowed for sustaining of the molten phase for a long time period. The released gases from concrete eliminated the sintering of UO2 and caused the formation of single large interior cavity in the UO2/concrete solidified mixture. Uplifting of the top surface of the mixture and the formation of a mountain-like protrusion, bearing a vent hole on its apex, resulted from significant internal pressure. Except for the bottom surface of the solidified mixture, which was continuous and glassy-like, all the other surfaces were porous. Analyses of selected samples revealed the presence of calcium uranate type compounds. Concrete constituents were well distributed throughout UO2. Magnesium did not participate in compound formation with UO2. Finally, dissolution of the concrete constituents in UO2 resulted in reduction of the internal-heat generation.