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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.
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.
L. Rodrigo, J.A. Sawicki, R.E. Johnson
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1410-1415
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30609
Articles are hosted by Taylor and Francis Online.
A postmortem analysis of samples of deactivated SAES St707 getter particles recovered from a glove box purification system was conducted to determine the cause for deactivation and eventual hydrogen capacity loss. Unused and used .getter samples were investigated by Auger Electron Spectroscopy (AES) and Mossbauer Transmission Spectroscopy (MTS) of 57Fe. Hydrogen absorption isotherms were measured to determine the extent of the hydrogen capacity loss, and the total impurity (0,N) loading levels were determined by vacuum fusion mass spectrometry. The effect of common gaseous impurities on the tritium-removal characteristics was investigated to determine the nature of impurity-getter interaction for different impurities. Hydrogen capacity loss observed in the purifier was found to be due to bulk nitriding, probably due to irreversible transformation of intermetallic Laves-phase Zr(Fe,V)2 to Zr4Fe2 (O,N)x. The temporary getter deactivation observed during operation of the purifier may have been caused by impurities such as CO, CO2 and volatile organics. Metallic Fe (considered to be responsible for dissociative chemisorption of H2) was found only on unused samples. A gradual loss of metallic Fe from the getter surface could also have contributed to getter deactivation.
