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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
Y. F. Li, M. Kondo, T. Nagasaka, T. Muroga, V. Tsisar
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 359-363
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12380
Articles are hosted by Taylor and Francis Online.
In this work, corrosion experiments on 9Cr-ODS and CLAM steels were carried out in static Pb-Li at 873 K for 250 h. Both steels showed weight loss and softening near the surface after the exposure. Tensile properties did not change and creep properties degraded slightly for 9Cr-ODS steel. In contrast, CLAM steel showed hardening by increase in tensile strength and creep rupture time, and decrease in minimum creep rate and reduction of area. The metallurgical analyses showed that the both steels were non-uniformly corroded by preferential corrosion at grain and sub-grain boundaries. Near the surface, carbides were lost and Cr was depleted to several tens of m depth. The depletion was heavier for 9Cr-ODS than for CLAM. The corrosion mechanism was proposed to be a loss of protective oxide layer followed by dissolution of Cr in matrix into liquid Pb-Li. The more pronounced corrosion effect on 9Cr-ODS than on CLAM may be due to finer grain and sub-grain size enhancing preferential attack by Pb-Li at the boundaries, or lack of Mn in 9Cr-ODS, which can form protective layers for CLAM.