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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
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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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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.
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 141-146
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32618
Articles are hosted by Taylor and Francis Online.
A review of the processes important to the behavior of aerosols during a severe reactor accident involving core melting shows processes leading to particle size change (agglomeration, condensation, and evaporation) and processes leading to removal of particles from the atmosphere (diffusion, sedimentation, thermophoretic, and inertial deposition). The NAUA model and computer code developed at the Karlsruhe Nuclear Research Center treats these processes in a hypothetical core melt accident. The NAUA code is based on first principles, without further restrictions. Its application to such an accident in a pressurized water reactor (Biblis B) shows that the mass of aerosol leaked from a containment building during an accident is strongly dependent on the aerosol source from the core and the existing steam conditions. Condensing steam is effective in reducing leaked aerosol mass. Most of the leakage would occur during the first 12 h of an accident; such leakage is not directly proportional to the aerosol source strength but tails off significantly as the initial aerosol concentration increases.