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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.
Iskender Atilla Reyhancan, Ayse Durusoy
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 202-207
Technical Paper | doi.org/10.13182/NSE11-96
Articles are hosted by Taylor and Francis Online.
In this study, the activation cross sections were, first, measured for the 144Sm(n,)141mNd reaction at six different neutron energies from 13.57 to 14.83 MeV. The fast neutrons were produced by using a neutron generator, through the 3H(2H,n)4He reaction. The cyclic activation technique was used as the irradiation and counting method. Induced gamma activities were measured using a high-resolution gamma-ray spectrometer equipped with a high-purity germanium detector. In the cross-section measurements, corrections were made regarding the effects of gamma-ray attenuation, dead time, fluctuation of neutron flux, and low-energy neutrons. The measured cross sections were compared with the results of model calculations (TALYS code).
