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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
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.
A. Pavlik, G. Winkler, M. Uhl, A. Paulsen, H. Liskien
Nuclear Science and Engineering | Volume 90 | Number 2 | June 1985 | Pages 186-202
Technical Note | doi.org/10.13182/NSE85-A17676
Articles are hosted by Taylor and Francis Online.
Using activation techniques, the excitation functions for the 58Ni(n,2n)57Ni and 58Ni(n,np + pn + d)57Co reactions were measured in the neutron energy range from 12.7 MeV, close to the (n,2n) threshold, to 19.6 MeV with an accuracy of typically ∼4.5 and ∼6%, respectively. In the 13.4- to 14.8-MeV energy range, the accuracy achieved for the cross sections of the above reactions was typically 2 and 3%, respectively. In addition, cross sections were measured for the 58Ni(n,p)58Co reaction in the 14-MeV region with an accuracy of typically ∼2%. The experimental results were compared with calculations based on the optical model, the compound nucleus model, and the exciton model of nuclear reactions. A quite satisfactory simultaneous reproduction of all experimental data, including the proton- and alpha-production spectrum, was achieved employing a unique set of model parameters. Moreover, the new (n,2n) cross sections provide an improved data base for reactor dosimetry and spectrum unfolding applications.