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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.
James H. P. Watson, Patrick Foss-Smith, Ray Lidzey
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 352-360
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3906
Articles are hosted by Taylor and Francis Online.
This paper describes the uptake of plutonium, 238Pu, by an adsorbent consisting of Brimac 216 natural carbon, a type of bone char. A strongly magnetic Brimac 216 fine powder produced by Lidzey has been shown to be an excellent adsorbent for many radionuclides. After the adsorption of the radionuclides has taken place, from solution onto the magnetic Brimac 216 powder, the powder, together with the adsorbed radionuclides, can be rapidly removed from suspension, as a concentrate, using high gradient magnetic separation (HGMS). A comparison is drawn between experimental results using the conventional column filter, with bone char as the adsorbent medium, and calculations for the HGMS process to treat 3.22 m3 of solution containing 8 mgl-1 of 238Pu and to remove the 238Pu from the suspension to reduce the effluent to less than the maximum concentration limit (MCL) for 238Pu, which is 0.74 Bql-1; however, the minimum concentration value used here is less than the MCL and is 0.0444 Bql-1 (7.006 × 10-14 gl-1 of 238Pu) and is denoted as the lower concentration level. Calculations indicate that HGMS is considerably faster than the column filtration method. This leads to a significant reduction in the time required to process the solution, even though the HGMS process is repeated a number of times. Also, the mass of adsorbent requiring long-term storage is much smaller for HGMS than for the column filtration method.