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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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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.
R. S. Pathania, E. G. McVey
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 178-190
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32840
Articles are hosted by Taylor and Francis Online.
Denting of steam generator tubes due to rapid corrosion of carbon steel support plates is a serious problem in many reactors on sea or brackish water locations. The objective of this program was to assess the effectiveness of sodium phosphate in minimizing corrosion and denting during leakage of seawater into a steam generator. Corrosion tests at 300°C were conducted on (a) electrically heated tubes of Alloy 800 equipped with crevice devices and exposed to dilute solutions of seawater and sodium phosphate, and (b) Alloys 800 and 600 tubes with carbon steel sleeves exposed to concentrated solutions of seawater and sodium phosphate + seawater. Exposure of heated tubes to seawater caused denting under carbon steel crevices. Addition of sodium phosphate to seawater prevented denting. Concentration factors within crevices were estimated by comparing the corrosion rates from heat transfer and isothermal tests; estimates ranged from 3700 to 6900, depending on the assumptions. Only shallow pitting was observed on the Alloys 800 and 600 tubes