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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
E. R. Hager, J. R. Lindgren, D. W. Graumann, M. G. Dunlap
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 968-973
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40159
Articles are hosted by Taylor and Francis Online.
A lithium blanket module (LBM), representative of a fusion reactor blanket module has been fabricated by GA Technologies Inc. via sub contract from Princeton Plasma Physics Lab under the sponsorship of the Electric Power Research Institute. The LBM consists of a cubical array of 92 cylindrical breeder rods, 2.54 cm in diameter. Each rod consists of an ∼59 cm long section of lithium oxide pellets clad in 0.03 cm wall Type 316 stainless steel tube followed by a 20 cm long stainless steel reflector rod. Reusable test rods in the 20 cm diameter central region incorporate activation foils for neutron dosimetry and aluminum clad pellets for tritium dosimetry. The breeder rods are contained in an enclosure structure which has provisions for insertion and removal of test rods and dosimeter wires. Procedures developed for fabrication and assembly of the rods and enclosure structure proved to be satisfactory and reliable and the work was done on schedule and within budget.
