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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.
A. D. Vaughn, R. I. Smith
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 146-152
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31129
Articles are hosted by Taylor and Francis Online.
The plutonium concentrations in mixed-oxide fuel rods containing distinct sizes of particulate plutonium oxide have been determined using high resolution gamma-ray spectrometry. The fuel rod enrichments were in the range 2 to 2.5 wt% in natural UO2. Individual rod enrichments were determined to within ±0.1 wt% by comparison with a known standard. Differences in plutonium iso-topic composition were discemable also, in addition to the differences in plutonium enrichment. The technique provides an inexpensive nondestructive method of determining in situ plutonium composition and content of assembled fuel rods, for purposes of quality assurance and accountability control.
