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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
Argonne researching “climate-ready” nuclear plant design
Scientists at Argonne National Laboratory have partnered with Washington state–based Energy Northwest to look at alternative ways to cool nuclear reactors as climate change impacts relied-upon water sources.
H. Huang, H. W. Xu, K. P. Youngblood, D. R. Wall, R. B. Stephens, K. A. Moreno, A. Nikroo, K. J. Wu, M. Wang, A. V. Hamza
Fusion Science and Technology | Volume 63 | Number 2 | March-April 2013 | Pages 190-201
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-TFM20-24
Articles are hosted by Taylor and Francis Online.
The National Ignition Facility point design uses a five-layer capsule to modify the X-ray absorption in order to achieve optimized shock timing. A stepwise copper dopant design defines the layer structure; however, the as-deposited Cu distribution is significantly altered during the CH mandrel removal by pyrolysis. The changes are significant: (a) Cu diffuses on average several microns, a distance more than an order of magnitude larger than predicted from the bulk diffusion data, and (b) the Cu distribution, as a result of diffusion, is highly heterogeneous, introducing a local variation of [approximately]0.06 at. % near the original layer interface. In this study, we developed quantitative techniques to measure Cu diffusion and explored its correlation to beryllium microstructures. Plausible diffusion mechanisms and mitigation methods will be discussed. These findings will enable more accurate evaluation of the expected target performance.