ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Curt M. Betts, Mark R. Galvin, Janet R. Green,† V. Melvin Guymon, Stephen M. Slater,‡, Andrew C. Klein
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 395-410
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34939
Articles are hosted by Taylor and Francis Online.
Currently, no comprehensive mechanistic model for the two-phase flow through a swirl vane steam separator is available. Therefore, an attempt has been made to develop an analytical model, using fundamental fluid mechanics, which is capable of predicting separator performance over a wide range of conditions. The developed model subdivides a typical boiling water reactor swirl vane steam separator into four distinct regions: the standpipe region, the swirl vane region, the transition region, and the free vortex region. In each region, the vapor and liquid components are treated separately and the behavior of individual droplets is determined from the drag force induced by the vapor continuum. The analytical model is used to first determine the vapor velocities throughout the separator. The drag force on the droplets is then determined, and the droplets are tracked through the separator in order to determine the exit position of each droplet. Separator performance can then be determined from this final position in terms of the fraction of droplets removed from the flow stream. In order to assess the validity of this model, the computer code SEPARATOR was developed. Among other capabilities, the code is capable of determining separator performance in terms of carryover, carryunder, and exit quality. However, due to the simplicity of the single-phase fluid treatment of the vapor continuum and the lack of data related to the average droplet diameter for flows of this nature, the results are not of significant quantitative value. The investigation performed does, however, suggest that the developed methodology, upon refinement of the single-phase fluids treatment, will yield quantitatively accurate results for nearly all separator operating conditions of interest.