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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
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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Nuclear Science and Engineering
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Fusion Science and Technology
Latest News
Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
Jeremy A. Burke, X. R. Wang, M. S. Tillack, ARIES Team
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 213-217
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12354
Articles are hosted by Taylor and Francis Online.
The current T-tube divertor design consists of modular helium cooled units. The individual units consist of a steel inner cartridge enclosed in a tungsten alloy outer structure. On top of the outer tube is a layer of pure tungsten armor. Past design and analysis of the T-tube divertor concept has shown that it can accommodate a heat flux up to 10MW/m2. With recent concerns that steady state or transient heat fluxes may be higher than this in the divertor region, the T-tube concept was modified so that it may accommodate higher heat fluxes.