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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Steven E. Skutnik, Man-Sung Yim
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 374-381
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14169
Articles are hosted by Taylor and Francis Online.
The effect of simplifications in nuclear fuel depletion analysis as well as the effect of cross-section uncertainties were evaluated as to their impact upon material attractiveness for weapons diversion purposes. The effect of simplified depletion models for material attractiveness evaluation was evaluated through a comparison of pressurized water reactor fuel for several benchmark cases, using experimentally measured values along with a two-dimensional lattice physics model (TRITON) and a point depletion model (ORIGEN-S). Simplifications such as the use of the ORIGEN-S depletion libraries and assumptions of homogeneous core enrichment were found to have a negligible impact on material attractiveness evaluation, particularly relative to uncertainties in experimental measurements; additionally, simplified irradiation power histories do not introduce unacceptable errors into the attractiveness evaluation. Finally, the overall sensitivity of material attractiveness and associated uncertainty was found to be greater for transuranic mixtures compared to plutonium as a function of both burnup and decay time; however, associated uncertainties are generally small and not prohibitive to material attractiveness discrimination. As a result, the use of simplified depletion models such as ORIGEN-S appears to be well justified for use in material attractiveness evaluation for proliferation resistance studies.