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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.
Kou-John Hong, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 80 | Number 4 | April 1982 | Pages 570-578
Technical Paper | doi.org/10.13182/NSE82-A18970
Articles are hosted by Taylor and Francis Online.
For transport problems with fine energy group structure, the group-to-group transfer, cross sections are usually quite anisotropic in the scattering angle. It is shown for neutron inelastic scattering that explicit use of the characteristic shape of these transfer cross sections permits more efficient and accurate numerical evaluation of their Legendre expansion coefficients than is afforded by existing techniques. In addition, transfer cross sections can often be well approximated by piecewise, low-order polynomials with which very accurate and simple expressions can be derived for the Legendre coefficients. This analytical approach both minimizes the access of nuclear data files and accurately determines even the higher order coefficients.