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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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University of Florida–led consortium to research nuclear forensics
A 16-university team of 31 scientists and engineers, under the title Consortium for Nuclear Forensics and led by the University of Florida, has been selected by the Department of Energy’s National Nuclear Security Administration (NNSA) to develop the next generation of new technologies and insights in nuclear forensics.
Dong-Jun Kim, Seong Dae Park, Dong Won Lee, Mu-Young Ahn
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 760-765
Technical Note | doi.org/10.1080/15361055.2017.1350487
Articles are hosted by Taylor and Francis Online.
After Conceptual Design (CD) Approval, Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) design is being updated for the preparation of the preliminary design phase, in which the manufacturability is the main concern based on the TBM-set model of CD phase. The major design parameters at the preliminary design phase were introduced. According to these parameters, the design of the main components such as first wall (FW), side wall (SW), and the breeding zone (BZ) was updated through the thermal-hydraulic analysis with ANSYS CFX v14.5. Also, the detailed design was performed on the back manifold (BM), TBM-shield, and the connecting supports. The internal channels for the He coolant and purge gas are designed in BM, in which the characteristics of the He channel were analyzed to meet the requirements of the temperature. The design concept of the connecting supports was described. The design of the TBM-shield is updated in order to simplify production and assembly.