ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
T. Yamamoto, Supardjo, T. Terai, F. Ono, S. Tanaka, M. Yamawaki
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 764-768
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST14-764
Articles are hosted by Taylor and Francis Online.
Hydrogen absorption-desorption properties of some uranium-rich alloys were studied to develop an advanced material for temporary tritium storage. The characteristics of U-33.3at%Zr were analogous to those of U-69.7at%Zr, while the durability to powdering was reduced according to a decrease of zirconium content. The U-5.7at%Al exhibited a similar behavior to that of pure uranium including powdering to much extent, though a slight decrease in decomposition pressure was observed. The U-25at%Si showed very small capacity of hydrogen in spite of the existence of uranium phase in this alloy.