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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Bryan A. Chin, Robert J. Neuhold, Jerry L. Straalsund
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 426-435
Technical Paper | Material | doi.org/10.13182/NT82-A26308
Articles are hosted by Taylor and Francis Online.
A nationally coordinated materials development program for fast breeder reactors is being conducted to improve the economy and reliability of replaceable core components. The program is comprised of three parallel paths, including reference alloys for present applications, second-generation alloys for near-term applications, and third-generation alloys for longer term applications. Reference alloy work is complete, with the major program emphasis being placed on qualification of titanium-modified Type 316 stainless steel (D9) for core applications. Ferritic alloy, HT-9, has been identified as an excellent duct material, and qualification of this alloy is being phased in as D9 work is completed. Another four alloys have been identified as potential cladding materials and are scheduled for completed development and application by 1988.