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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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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.
P. A. Finn, J. P. Webb
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 371-376
Safety; Measurement and Accountability; Operation and Maintenance; Application | doi.org/10.13182/FST92-A29773
Articles are hosted by Taylor and Francis Online.
Irradiated tritium targets may be handled in the Main Cell of the Hot Fuel Examination Facility (HFEF) to support transient safety tests for the New Production Reactor (NPR). To support this activity, the systems at HFEF were examined with the goal of minimizing tritium contamination of HFEF while achieving the requirements of the transient tests. Conceptual design descriptions are provided for required experimental systems and tritium recovery systems.
