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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
R. M. Hunt, M. Narula, M. A. Ulrickson, T. T. Martin, A. Ying
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 38-42
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8872
Articles are hosted by Taylor and Francis Online.
Understanding the manner in which the First Wall Qualification Mockup (FWQM) responds structurally to simulated ITER conditions is important to the establishment of a reliable first wall. This paper provides a thermal and structural response analysis for the first round of qualification tests performed at Sandia National Laboratories. The results display the stresses and strains created in the FWQM as a result of the thermal expansion that occurred when subjected to cyclic heat flux under simulated ITER normal and MARFE conditions. From this structural response, further insight may be gained into the likelihood of fatigue failure of the Beryllium//CuCrZr interface once the first wall is in operation in ITER. While fully determining the reliability of this joint is beyond the scope of this study, some suggestions are made as to how this topic might be addressed with further research. Also investigated are the thermal patterns seen during testing that indicated slight variation from the intended test parameters. It is shown that these disparities from the ideal test parameters do not significantly affect the qualification of the FWQM.