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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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
S. E. Soliman, D. L. Youchison, A. J. Baratta, T. A. Balliett
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 346-352
Technical Paper | Material | doi.org/10.13182/NT91-A34595
Articles are hosted by Taylor and Francis Online.
Neutron effects on the mechanical properties and the microstructures of borated stainless steel are studied by irradiating three borated stainless steel batches to different radiation levels (from 1 × 1013 to 1 × 1017 n/cm2). Each batch includes samples varying in boron content from 0.25 to 2.01 wt° and manufactured by two different processes: a powder metallurgical and a conventional wrought technique, which meet the requirements of American Society of Testing and Materials Standard A-887 grades A and B, respectively. A total of 50 tensile specimens, 81 Charpy V-notch samples, and 17 metallographic specimens are used for this purpose. In general, the mechanical properties of samples manufactured by both the powder metallurgy and the wrought techniques show almost no change in mechanical properties with fluence. In addition, no evidence of helium effects are observed during the investigation. Further studies on helium formation in this material during irradiation are ongoing.