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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.
Juan J. Manzano-Ruiz, David Gordon Wilson
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 275-286
Technical Paper | doi.org/10.13182/NSE84-A18582
Articles are hosted by Taylor and Francis Online.
A test rig was built to run steady-state experiments with air/water mixtures at low pressure (42 kPa), and to determine the performance characteristics of two-phase flow through a centrifugal pump. Application is to a loss-of-coolant accident situation in nuclear reactor power plants if a large break in one of the primary pump legs took place. Two feasible accident conditions were tested; first- (forward flow and rotation) and third-quadrant (reverse flow and rotation) conditions. A significant head-pump degradation process was observed in the first-quadrant operation for increasing amounts of gas supplied, whereas in the third quadrant no difference in performance was detected with respect to single-phase flow and up to an inlet volumetric quality of 20%. The data gathered have been correlated in terms of a defined head-loss ratio, flow coefficient, and volumetric quality, which facilitates its use in predicting pump performance in similar designs of different scale.