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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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
Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
Daniel López, Javier Sanz, Francisco Ogando
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 252-257
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14143
Articles are hosted by Taylor and Francis Online.
During the IFMIF/EVEDA phase, a 125 mA and 9 MeV deuteron prototype accelerator will be designed and tested for the final IFMIF project. Deuteron losses will occur during operation of the accelerator at several components as well as at the beam stopping, leading to material activation induced by deuterons and/or by secondary neutrons, depending on the location. This work is focused on the residual dose rate assessment inside the accelerator vault due to the radioactive inventory induced in the main accelerator components, the outside concrete structures of the accelerator vault, and the concrete-made local shielding of the beam dump. The results will be useful for maintenance work planning, identifying hot areas in the accelerator region. The adopted computational procedure uses MCUNED for determination of spatial distribution of deuteron and neutron fluxes, ACAB for activation calculations, and MCNPX for transport of decay gammas. Deuteron transport cross sections are taken from TENDL-2010 and decay and activation cross-section data from EAF-2007.