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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
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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.
M. Oyaidzu et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 638-641
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A1006
Articles are hosted by Taylor and Francis Online.
The annihilation behaviors of radiation defects in neutron-irradiated LiAlO2 were investigated by means of Electron Spin Resonance (ESR). It was found that the annihilation of radiation defects consisted of two processes, the fast and the slow processes. The activation energies of them were determined to be 0.14 ± 0.01 eV and 0.58 ± 0.01 eV, respectively. The F+-center was found to act as a trapping site of tritium by comparing its annihilation behavior with that of tritium release. Taking the results obtained in the present and the previous works in consideration, it can be said that the annihilation process of oxygen vacancies is of very important because tritium release from the bulk of a breeder starts just after the slow annealing process becomes dominant. Therefore, to understand the slow annihilation process of radiation defects is an important key to clarify the mechanism of tritium release from ceramic breeder materials.
