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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
H. Xu, K. P. Youngblood, H. Huang, J. J. Wu, K. A. Moreno, A. Nikroo, S. J. Shin, Y. M. Wang, A. V. Hamza
Fusion Science and Technology | Volume 63 | Number 2 | March-April 2013 | Pages 202-207
Technical Paper | Selected papers from 20th Target Fabrication Meeting, May 20-24, 2012, Santa Fe, NM, Guest Editor: Robert C. Cook | doi.org/10.13182/FST13-TFM20-16
Articles are hosted by Taylor and Francis Online.
The point design of beryllium capsules includes three Cu-doped layers in a 160-m-thick beryllium shell to achieve the desired X-ray absorption profile. The beryllium capsules were deposited on glow discharge polymer mandrels using a magnetron sputtering process. Cu diffusion during pyrolysis to remove the mandrels after coating has caused nonuniform distribution of Cu along the azimuthal direction due to inhomogeneous diffusion. This nonuniformity along the azimuthal direction could lead to Rayleigh-Taylor instability during capsule implosion. One of the methods to solve this issue is to incorporate a beryllium oxide diffusion barrier layer at the beryllium-Cu-doped-beryllium layer interfaces. In situ and ex situ beryllium oxide layers have proved to be effective in stopping Cu diffusion. This paper will focus on the approaches we have developed to characterize the in situ and ex situ oxide barrier layer thickness by using a combination of Auger electron spectroscopy profiles and Rutherford backscattering spectrometry measurements.