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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Star Trek or Planet of the Apes?
Craig Piercycpiercy@ans.org
These days, the ship of civil nuclear technology we are all aboard is sailing through a turbulent passage. The winds and currents are favorable, but there are swells ahead: steep energy-demand projections, buoyant equity valuations, splashy announcements, a generational realignment of nuclear policies and institutional norms.
Part of the reason we chose “Building the Nuclear Century” as the theme for this year’s Winter Conference was to put some ballast in the hull of the nuclear conversation.
Advanced nuclear fission and fusion energy development are accelerating, both here and around the world. And yet, at least in the U.S., we are still years away from connecting commercial Gen IV systems to our grid.
In a world growing increasingly impatient, how do we stay on task and deliver? There are three ingredients to success.
D. S. Lee, S. A. Musa, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 77 | Number 7 | November 2021 | Pages 875-882
Student Paper Competition Selection | doi.org/10.1080/15361055.2021.1920783
Articles are hosted by Taylor and Francis Online.
Our group has recently developed and studied “finger”-type divertors that are a simplified version of the helium-cooled modular divertor with multiple jets (HEMJ) using coupled computational fluid dynamics and thermal stress simulations. Such a simplified geometry could reduce complexity and cost given the large number of fingers required to cover the total divertor target area. Previous experimental studies for this simplified flat design reported lower heat transfer coefficients and higher pressure drops than the HEMJ, contrary to numerical predictions. Subsequent measurements determined that the original test section had significant dimensional variations in the jet exit holes. A new test section was therefore manufactured and tested in the Georgia Tech (GT) helium loop. The experimental results presented here for this test section at maximum heat flux of 7.1 MW/m2 are in good agreement with numerical predictions. Correlations developed from these experimental data are extrapolated to predict the maximum heat flux that can be accommodated by the flat design and the coolant pumping power requirements under prototypical conditions. Finally, numerical simulations are used to estimate the sensitivity of the flat design to geometric variations typical of manufacturing tolerances and variations in the gap width.