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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
William Primak
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 29-34
Technical Paper | doi.org/10.13182/NSE80-A18705
Articles are hosted by Taylor and Francis Online.
Graphite rods and vitreous silica blocks were exposed to the neutrons generated in a spallation source having a large flux component in the 100-MeV region. The electrical conductivity of the former and the dilatation of the latter were measured. The ratio of the damage rate in silica to that in graphite exceeded that reported for fission neutrons, and this is attributed to the scattering cross sections of carbon falling more in the neutron high-energy region than do those of silicon and oxygen. Within our knowledge of the fluxes and their spectra and the yield functions, no great enhancement of the damage rate is found as compared to that which would be calculated from simple isotropic scattering.
