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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
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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Fusion Science and Technology
Latest News
DOE issues RFQ for clean-energy projects at WIPP
The Department of Energy has issued a request for qualifications (RFQ) for interested parties that are looking to establish carbon pollution–free electricity (CFE) projects at its Waste Isolation Pilot Plant site in New Mexico.
F. Cardoso, C. Pereira, M. A. F. Veloso, C. A. M. Silva, R. Cunha, A. L. Costa
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 338-342
Modeling and Simulations | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13442
Articles are hosted by Taylor and Francis Online.
Among the projects of IV generation reactors available nowadays, the (High Temperature Reactors) HTR, are highlighted due to their desirable characteristics and they have been studied by the Instituto Nacional de Ciências e Tecnologia de Reatores Inovadores/CNPq(Brazil). For this work, it evaluated the neutronic behavior and fuel composition during the burnup using the codes (Winfrith Improved Multi-Group Scheme) WIMSD5 and the MCNPX2.6, inserting different percentages of reprocessed fuel in the core. The fuel type “C” coming from Angra-I nuclear power plant, in Brazil, enriched with 3.1% was burnt by three typical cycles and then reprocessed. It recovered (Pu) and minor actinides (MA)being neptunium (Np), americium (Am), curium (Cm), and processed six different fuels varying percentage insertion of reprocessed fuel and enrichment uranium. It analyzed the multiplication factor, temperatures reactivity coefficients, and the composition during the burnup. The results showed, in the analyzed conditions, only one of these fuels is possible to be used. To compare, a reference fuel using 15% enrichment (235U) was too evaluated.