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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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May 2025
Latest News
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.
CH. Adelhelm, H.U. Borgstedt, J. Konys
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 541-545
Material Engineering — Behavior | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40095
Articles are hosted by Taylor and Francis Online.
The application of vanadium alloys as structural materials for the first wall or blanket of a fusion reactor will depend strongly on their compatibility with the coolants and breeding materials included in the blanket system. In the case of the use of liquid alkali metals, lithium offers the advantage of being an excellent heat transfer fluid as well as an excellent breeder of tritium. For the studies of the corrosion behaviour of V 3Ti 1Si in flowing lithium, a pumped lithium loop was designed and constructed. The results gained so far indicate that this vanadium alloy is, from the point of view of compatibility with liquid lithium up to 823 K, a promising material for the application in fusion reactor technology.
