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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.
K. Kotoh et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 173-178
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8897
Articles are hosted by Taylor and Francis Online.
For the purpose of developing a cryogenic pressure swing adsorption (PSA) system, we have been studying the breakthrough behavior of hydrogen isotopes with synthetic zeolite packed-beds under conditions specified for designing a PSA process. Previously, we have reported that overshooting breakthrough curves of tracer D2 in H2 were obtained from experiments of exchange-adsorption carried out after replenishing a packed-bed column with H2 from its outlet, following evacuation for a given period. The overshooting behavior is considered due to the enrichment of the heavier component D2 not only in the adsorption process but also in the evacuation process. In the next work, we have examined the effects of priming flow rates and evacuation periods on the overshooting behavior, using synthetic zeolites 5A and 13X packed-bed columns. In this paper, it is reported that the overshooting profile depends on the conditions of evacuation but not sensitively on the mass flow rates in replenishing process. The overshooting is advantageous for the adsorption process, because of improvement of the breakthrough time. Since the replenishing period is shortened proportionally to the priming flow late, the insensitive dependence of the overshooting on the priming flow rate is favorable to the PSA process, resulting in saving the time for replenishing process.
