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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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Latest News
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.
C. E. Kessel, T. Bohm, M. S. Tillack, P. Titus, Y. Zhai
Fusion Science and Technology | Volume 77 | Number 7 | November 2021 | Pages 519-531
Technical Paper | doi.org/10.1080/15361055.2021.1909988
Articles are hosted by Taylor and Francis Online.
Restraining the size of fusion power plants is considered an important avenue to make them a competitive energy source among other forms of energy production. The most critical contributor to the size of a tokamak is the inboard radial build, composed of multiple components with various functions. This build is the ultimate limit to size reduction. The Fusion Nuclear Science Facility is reviewed and each element of the inboard build is described, showing that the build, including breeding blanket, structural ring, vacuum vessel, low-temperature shield, and toroidal field and central solenoid (CS) coils, contributes 2.9 m of build, with 0.6 m of bore hole inside the CS coil, or 3.5 m to reach the plasma scrape-off layer. This implies that it would be challenging to make a significantly smaller build and simultaneously meet all the engineering requirements.