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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.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
R. R. Paguio, A. Nikroo, K. M. Saito, J. F. Hund, E. R. Castillo, N. M. Ravelo, K. Quan
Fusion Science and Technology | Volume 55 | Number 4 | May 2009 | Pages 450-455
Technical Paper | Eighteenth Target Fabrication Specialists' Meeting | doi.org/10.13182/FST09-A7425
Articles are hosted by Taylor and Francis Online.
Resorcinol formaldehyde (RF) foam shells are needed for direct-drive inertial confinement laser fusion experiments at the University of Rochester OMEGA laser facility. As previously reported, the addition of long-chained polymers to the fabrication process has improved shell wall uniformity, but this change has led to a lower yield (from ~40 to ~15%) of shells that are gas retentive after the application of glow discharge polymer (GDP) using the standard deposition technique. We have improved this yield by modifying the coating conditions of the GDP overcoating process by modifying the background coating pressure from the constant 75 mTorr to using a two-step coating process of a high-pressure coating at 250 mTorr followed by low-pressure coating of 75 mTorr. This modification has improved the yield of the gas retention on the styrene-butadiene-styrene RF shells from ~15 to ~60%. We have found that the surface roughness of these shells is also improved from ~45 nm root-mean-square (rms) to ~20 nm rms. This technique, however, leads to a slight shrinkage of shells, which will be described.