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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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.
Jean-Louis Bernard, Georges S. Slama
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 136-147
Technical Paper | Material | doi.org/10.13182/NT82-A33059
Articles are hosted by Taylor and Francis Online.
The need exists to define a fatigue crack growth design curve in an air environment for austenitic stainless steels in the temperature range of 300°C, which is the operating temperature range of pressurized water reactors. In the present study, elements to determine such a curve in a deterministic way are developed. In particular, effects of R ratio (Kmin/Kmax) are reviewed, and high R ratio tests, which were lacking, have been performed. To take into account R ratio effects, a relationship giving realistic predictions in accordance with high R ratio experiments is determined. A design curve, defined from a large compilation of results from several laboratories, allows a conservative calculation of all known fatigue crack growth tests on austenitic stainless steels in the temperature range of 300°C.
