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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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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.
Marco Ferrari, Massimo Furrer, Giorgio Simbolotti, Carlo Talarico
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1011-1015
Fusion Blanket and Shield Technology | doi.org/10.13182/FST96-A11963069
Articles are hosted by Taylor and Francis Online.
Following a preliminary test campaign (200 thermal cycles) on a solid breeder blanket mockup, an extended test campaign (about 1000 thermal cycles) has been carried out by ENEA. The duration of the test campaign represents a significant fraction of the blanket module lifetime in the ITER device. In particular, these out-of-pile experiments have been performed in order to test (both functional and endurance testing) the thermal-hydraulic and thermo-mechanical performance of a water cooled breeder-in-tube blanket mockup (1-PIN) using Li2ZrO3 pebbles as a breeder material.
The test campaign has been completed and the resulting data concerning thermal and thermal-hydraulic parameters have been elaborated and analyzed by means of a comparison with theoretical predictions based on a proper thermal-hydraulic model.
The post test examination of the pebbles is in progress in order to investigate the thermo-mechanical behavior of the breeder material under cycling.
The paper deals with the first part of the results.
