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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.
J. W. Sterbentz, J. E. O'Brien, R. A. Anderl, G. R. Smolik, D. A. Petti, K. A. McCarthy
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 773-778
Chamber Technology | doi.org/10.13182/FST01-A11963332
Articles are hosted by Taylor and Francis Online.
A preliminary design is presented for the FLIQURE or Fusion LIQUid Release Experiment. This experimental system is designed to measure the mobilization of tritium, fluorine, and other constituents in molten Flibe following trace neutron irradiation at fusion-relevant temperatures (500-1000°C). Trace neutron irradiation is achieved using a spontaneous fission 252Cf source that produces a relatively uniform concentration of tritium in the Flibe. The experimental goals aim to better understand the mechanisms, mobilization rates, and physiochemical forms of tritium mobilized from the Flibe along with other potentially detectable radioactive isotopes and toxic-material species under inert-gas, air, and steam-ingress conditions. System design details are discussed which include neutronic studies to optimize tritium production, thermal design to maintain and isolate molten Flibe, and instrumentation to meet experimental goals.
