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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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May 2025
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. Y. Chang, S. K. Loyalka, D. H. Timmons
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 313-315
Technical Note | doi.org/10.13182/NSE79-A20154
Articles are hosted by Taylor and Francis Online.
A modified version of the LASER computer code is constructed by using Gear's method for isotopic burnup calculations. It is noted that the original version of the LASER code (as supplied recently by the Argonne Computer Code Center) errs in computation of 241Pu concentration due to a minor programming oversight. This error is corrected, and it is found that the corrected LASER and the modified LASER provide results that agree quite well. For the same calculations, the modified LASER requires only two-thirds the central processor unit time compared to the original (corrected) LASER (on an IBM 370/158). Also, the modified LASER has simpler and more general provisions for handling burnup calculations.
