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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.
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.
W. F. Murphy, H. E. Strohm
Nuclear Technology | Volume 4 | Number 4 | April 1968 | Pages 222-229
Technical Paper and Note | doi.org/10.13182/NT68-A26320
Articles are hosted by Taylor and Francis Online.
Segments of Type-304L stainless-steel cladding from irradiated EBR-II fuel elements have been used for burst tests from room temperature to 1000°C. The cladding had accumulated exposures of (0.5 to 1.4) × 1022 n/cm2 (> 0.1 MeV) at temperatures between 370 and 500°C. In burst tests at ≤ 700°C, the greater strength was on the lower half of the irradiated cladding where the irradiation temperature was < 475°C. Tests at 800, 900, and 1000°C each showed uniform strength along the lengths of the cladding. The strength of the irradiated specimens decreased most rapidly with temperatures between 400 and 700°C. Unirradiated specimens were weaker than irradiated ones below 700°C; above 700°C, the unirradiated specimens were slightly stronger. The irradiated and the unirradiated specimens had low uniform strain (∼1 and ∼10%, respectively) at temperature of ∼ 400 to 500°C.