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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Texas-based WCS chosen to manage U.S.-generated mercury
A five-year, $17.8 million contract has been awarded to Waste Control Specialists for the long-term management and storage of elemental mercury, the Department of Energy’s Office of Environmental Management announced on November 21.
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.
