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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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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.
J. H. Nadler, G. H. Miley, Y. Gu, T. Hochberg
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1639-1643
Plasma Engineering | doi.org/10.13182/FST92-A29955
Articles are hosted by Taylor and Francis Online.
There is considerable demand in the scientific community for a neutron generator with an output of 105–106 n/s that can be turned on or off, emits fusion neutrons, is self-calibrating, and can offer portable operation [1,2]. This paper will describe how an IEC-based neutron generator could satisfy these demands. Experimental data and modeling is presented for operation to the 105 n/s range. Direct extrapolation of the results indicate that with modest extension of operating parameters operation can be achieved in the 106–107 n/s range; with more aggressive modifications operation in the 108–10 n/s range can be possible.