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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
S. Gordeev, L. Stoppel, R. Stieglitz, M. Daubner, F. Fellmoser
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 301-308
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8918
Articles are hosted by Taylor and Francis Online.
The target assembly of the International Fusion Materials Irradiation Facility (IFMIF) consists of a nozzle, which has to form a stable lithium jet. Therefore, a flat uniform velocity distribution at the nozzle outlets cross-section with a simultaneously low turbulence intensity is required to ensure a safe operation. These boundary conditions necessitate a detailed knowledge on the turbulent flow in contraction nozzles in order identify turbulence models accurately predicting experimental findings within the velocity range of interest for nuclear target and hence can then act as design optimization tool.In order to validate commercially available Computational Fluid dynamic codes (CFD) and the turbulence models incorporated in them a series of experiments using water as model fluid are conducted in the Liquid-Metal-Laboratory KALLA at the research center Karlsruhe. A number of turbulence models with different extensions for the near wall treatment were tested versus the experimentally obtained data. Based on this comparison a hydraulic analysis of the contraction nozzle flow is performed taking into account the relaminarization of the accelerated flow, the occurrence of secondary motions and their impact on the development of the boundary layer. In summary the V2F turbulence model exhibits the best agreement between numerical and experimental data and thus can be considered to be most suitable for the simulation of the accelerated nozzle flow for free surface target applications.