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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Philipp Schmuck
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 314-325
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33729
Articles are hosted by Taylor and Francis Online.
An efficient and simple method to compute one-dimensional steady-state and transient turbulent single-phase flows across singularities (e.g., sudden contractions or expansions in ducted flows) is presented. This method accounts for the effective inertia of a fluid at a constriction and the irreversible pressure losses caused by recirculation zones generated near a singularity. For selected singularities of technical interest, algebraic expressions for the equivalent inertia lengths and the hydraulic resistance coefficients are presented. The implementation of the method into one-, two-, and three-dimensional numerical fluid dynamics codes is explained and the limitations of the method are discussed. The method is also extended to two-phase flow where additional flow parameters characterizing the momentum exchange between the phases play a role.