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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.
B. Strohmaier, M. Uhl, W. K. Matthes
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 368-384
Technical Paper | doi.org/10.13182/NSE78-A27164
Articles are hosted by Taylor and Francis Online.
Average neutron-induced reaction cross sections for 134–138Ba (the barium isotopes of mass number 134 through 138) for incident energies between 20 keV and 20 MeV have been calculated by means of the optical and the statistical model with consideration of preequilibrium emission. The calculations comprise the total, the nonelastic, the differential elastic, and the (n,γ), (n,xnγ), (n,pγ), (n,pnγ), and (n,npγ) cross sections, as well as the production spectra of neutrons, protons, and gamma rays. For the model calculations, a consistent set of parameters based as much as possible on experimental data was employed. The computed cross sections are compared to available experimental results. Since such theoretical calculations are also of importance for nuclear data evaluation in cases where no experimental data exist, accuracy estimates of the predicted cross sections are given.