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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.
M. Kowaka, H. Nagano, T. Kudo, Y. Okada, M. Yagi, O. Takaba, T. Yonezawa, K. Arioka
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 394-404
Technical Paper | Materials | doi.org/10.13182/NT55-394
Articles are hosted by Taylor and Francis Online.
It was shown that a modified Huey test, i.e., a 24-h immersion in boiling 40% HNO3, is able to exactly detect the susceptibility to intergranular corrosion of Alloy 600, which is correlated with intergranular stress corrosion cracking (IGSCC) behavior in high temperature water containing small amounts of chloride ions. Chromium content at the regions adjacent to grain boundaries in sensitized Alloy 600 was analyzed as ∼3% by the measurement of magnetic susceptibility. Heat treating Alloy 600 at low temperatures, e.g., at 700°C for 15 h, improves the IGSCC resistance to both high temperature water and caustic solutions by constructing suitable micro structures resistant to sensitization, in which chromium carbides precipitate predominantly in the matrix instead of grain boundaries.