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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
Atomic Canyon partners with INL on AI benchmarks
As interest and investment grows around AI applications in nuclear power plants, there remains a gap in standardized benchmarks that can quantitatively compare and measure the quality and reliability of new products.
Nuclear-tailored AI developer Atomic Canyon is moving to fill that gap by entering into a new strategic partnership with Idaho National Laboratory to develop and release the “first comprehensive benchmark suite for evaluating retrieval-augmented generation (RAG) and large language models (LLMs) in nuclear applications.”
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.
