ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
J. R. Phillips, T. K. Marshall
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 222-228
Technical Paper | International Safeguard / Fuel | doi.org/10.13182/NT77-A31929
Articles are hosted by Taylor and Francis Online.
A precision gamma-scanning system was applied to the nondestructive determination of the isotopic distributions of 103Ru and 106Ru in two failed (U,Pu)O2 fuel pins irradiated in the Experimental Breeder Reactor II. Significant differences in the two distributions were measured that were related to the half-lives of the two ruthenium isotopes. The two distributions can be used to determine the relative times at which the ruthenium deposits were formed within the fuel material. This information may be used to determine nondestructively the changes within the central void region over a period of several irradiation cycles.
