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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.
Eberhard Teuchert, Hans Joachim Rütten, Heinz Werner
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 374-383
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A32035
Articles are hosted by Taylor and Francis Online.
For the pebble-bed high-temperature reactor, a wide choice is available for the design of the fuel elements and for the reactor fueling scheme. This flexibility has been utilized for the conception of different possibilities for the closure of the thorium fuel cycle. The easiest scheme is mixed-oxide recycling with repeated recycling of 236U. Loading recycle fuel into separate elements without thorium reduces the uranium ore demand by 13%. Entire separation of the feed and breed circuits brings another reduction of 5%. Furthermore, the feed-breed cycle allows the production of 233U for the near-breeder variant. This variant achieves a conversion ratio of 0.97, and it represents a possible choice for efficient protection of uranium ore resources. Within the span of uncertainties in the cost assumptions, fuel cycle costs are found to be comparable for all considered cycles, including the near-breeder.
