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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.
P. A. Egelstaff, P. Schofield
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 260-270
Technical Paper | doi.org/10.13182/NSE62-A26066
Articles are hosted by Taylor and Francis Online.
The magnitude of the scattering cross section for slow neutrons by atomic systems (gases, liquids, and polycrystalline solids) is governed by the correlated motions of atoms in the system. A major contribution to the scattering is determined by the motion of single atoms. The dominant part of this contribution is determined by the velocity autocorrelation function for an atom in the system. The aim of this paper is (i) to show how the autocorrelation function can be derived from experimental scattering data for small momentum transfers and (ii) to give methods of evaluation of the corresponding part of the cross section for all momentum and energy transfers in terms of the experimentally observed quantities. The methods are chosen to minimise computational difficulties and inaccuracies. The comparison of the recomputed data with the experimental results permits the estimate of other contributions to the scattering. Some simple examples of these methods are given, and the relevance of this work to thermal neutron transport calculations is mentioned.