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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.
T. A. Wareing, W. F. Walters, J. E. Morel
Nuclear Science and Engineering | Volume 118 | Number 2 | October 1994 | Pages 122-126
Technical Note | doi.org/10.13182/NSE94-A28541
Articles are hosted by Taylor and Francis Online.
Recently, a new diffusion synthetic acceleration scheme was developed for solving the two-dimensional Sn equations in x-y geometry with bilinear-discontinuous finite element spatial discretization, by using a bilinear-discontinuous diffusion differencing scheme for the diffusion acceleration equations. This method differed from previous methods in that it is unconditionally efficient for problems with isotropic or nearly isotropic scattering. Here, the same bilinear-discontinuous diffusion differencing scheme, and associated multilevel solution technique, is used to accelerate the x-y geometry Sn equations with linear-bilinear nodal spatial differencing. It is found that for problems with isotropic or nearly isotropic scattering, this leads to an unconditionally efficient solution method. Computational results are given that demonstrate this property.