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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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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.
G. Rodin, Y. L. Hwang, R. Carrera, R. Mohanti, C. A. Ordonez
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1745-1749
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29594
Articles are hosted by Taylor and Francis Online.
A relatively simple and low cost first wall system concept for a fusion ignition experiment is proposed and analyzed here. The basic idea is to use plasma gun technology to spray a thin layer of beryllium over the inside surface in the vacuum vessel. This concept is analyzed for the fusion ignition experiment IGNITEX. To minimize peaking factors during regular operation, a continuous limiter plasma control is envisioned. With presently available data on beryllium coatings, a thermomechanical stress analysis during a major disruption process at ignition is analyzed. It is concluded that the basic concept of the full beryllium coating over the vacuum vessel is feasible on a preliminary basis. Some research and development needs in this area are discussed.