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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.
Meeting Spotlight
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.
R. C. Lloyd, B. M. Durst, E. D. Clayton
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 164-169
Technical Paper | doi.org/10.13182/NSE79-A20407
Articles are hosted by Taylor and Francis Online.
A series of experiments was performed to determine the effect of soluble neutron absorbers on the criticality of water-moderated latticed assemblies. The soluble absorbers used were boron, gadolinium, and cadmium. These materials were mixed with the moderator and reflector of lattices of 4.3-wt%-235U-enriched UO2 fuel pins with stainless-steel cladding. Lattice spacings of 22.9, 27.9, and 33.0 mm, center-to-center, were measured to determine the critical number of rods. The value of keff was computed for each assembly on which criticality was determined. The computed keff value were up to ∼2% above unity in some cases, with the average value for the entire series being 1.007.