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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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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.
Shih-Jen Wang, Ming-Song Lin
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 156-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34553
Articles are hosted by Taylor and Francis Online.
The characteristics of xenon dynamics are simulated, and related parameters are identified in the Taiwan Research Reactor. A xenon transient for a 20% stepwise decrease from 85.6% rated power is performed and simulated with design data. The trends in the moderator levels are similar in the test and in the simulation. However, there are discrepancies in the magnitude and shape. Because no reactivity feedback occurs for 2 h after the power change, except for xenon poisoning, a parameter optimization method is applied to identify the migration area and the initial neutron flux by minimizing the integrated square error of the moderator level from 2 to 20 h after the power change. The optimized moderator level fit the test result very well, and the identified parameters are reasonably close to the experimental data.