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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
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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.
Y. Asaoka, H. Moriyama, Y. Ito
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1944-1948
Material and Tritium | doi.org/10.13182/FST92-A30004
Articles are hosted by Taylor and Francis Online.
The production behavior of irradiation defects in lithium oxide was studied by in-situ luminescence measurement under He+ beam irradiation. The luminescence peaks of 380 nm and 340 nm, which were associated with the production of F+ and F0 centers, respectively, were measured under various conditions such as temperature changes, and the production mechanism and kinetics of these irradiation defects were determined. The F+ centers are rather directly produced from Li2O with the partners of O- interstitials under Coulomb interactions while the F0 centers are produced with O2 through some diffusion processes. Although the F+ production dominates at lower temperatures, the F0 production increases with increasing temperature. The F0 centers would play an important role in the tritium recovery from ceramic breeder materials at actual blanket conditions.