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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.