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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.
K.M. Nikbin, G. A. Webster, N. Mitchell
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1905-1908
Magnetic | doi.org/10.13182/FST92-A29997
Articles are hosted by Taylor and Francis Online.
A single rectangular conductor jacket, including the surrounding insulation, has been modelled using finite element computational techniques. Such jackets are typical of the situation in a force flow cooled superconducting coil, where the jacket encloses the current carrying cable and the liquid helium coolant. Elliptical shaped cracks in the jacket have been included in the model to evaluate the stress intensity factors at the crack tip for three crack sizes at three different locations. Results using 3D finite elements are presented for a typical semi-elliptical surface crack in a single conductor jacket under tensile loading. It has been found that mesh and element sizes contribute to the variation in the values of the stress intensity factors calculated but that the relative accuracy of the results is generally within ±5%.