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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
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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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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.
K. Cheuk Chan, Harvey J. Amster
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 434-437
Technical Note | doi.org/10.13182/NSE76-A26931
Articles are hosted by Taylor and Francis Online.
Exact elementary functions for the value and first two lethargy derivatives of the collided neutron flux at source lethargy have been derived previously for a monoenergetic plane source in hydrogen, and the results have been used both to test calculational methods and to synthesize an elementary function for the entire spatially dependent slowing down distribution. In this Note, the exact elementary functions at source lethargy are generalized to allow: (a) any number and thicknesses of homogeneous slabs with faces parallel to the source plane, (b) each slab to be composed of any mixture of isotopes with arbitrary energy-dependent elastic scattering and absorption cross sections, and (c) any number of equally spaced cosine-weighted source planes.