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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
W. P. Barthold, J. C. Beitel, P. S. K. Lam, Y. Orechwa, S. F. Su, R. B. Turski
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 525-528
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32361
Articles are hosted by Taylor and Francis Online.
To avoid high energy releases in unprotected loss-of-flow accidents, cores can be designed such that the removal of sodium would add only a small amount of reactivity or even a negative reactivity to the reactor. Reduction in sodium void reactivity can be achieved by changing either the geometry or composition of the core. Pancake, modular, and heterogeneous core configurations were investigated. Heterogeneous cores showed sodium void reactivities in the 2-dollar range with only small penalties in doubling time when compared with the equivalent homogeneous cores. Liquid-metal fast breeder reactors using U-Th fuel in the form of metal, oxide, or carbide show negative sodium void reactivities but doubling times above 30 yr.