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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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.
Qi Xu, T. Nagasaka, T. Muroga
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 609-612
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1555
Articles are hosted by Taylor and Francis Online.
Fe-Cr-W based low activation ferritic steels are widely regarded as promising blanket structural materials for fusion reactors, while liquid lithium breeder/coolant concept provides an attractive option for high efficiency and simplicity of blanket system. However, past compatibility tests of ferritic steels with liquid lithium were almost limited to conventional Fe-Cr-Mo steels. In this study, the corrosion behavior of the candidate reduced activation ferritic steel, JLF-1(Fe-9Cr-2W-0.1C) in lithium was investigated. Static immersion tests were carried out using coupon specimens (16 × 4 × 0.25 mm) at 873K and 973K for 100hr. At 973K, the phase transformation from martensite to ferrite resulted in decrease in hardness from 250 to 140Hv. This seemed to be caused by depletion of C. Examinations of binary Fe-Cr and pure iron were also carried out for comparison with JLF-1.